序章

原子炉は、核分裂核連鎖反応または核融合反応を開始および制御するために使用される装置です。原子炉は、原子力発電所での発電や船舶の原子力推進に使用されます。核分裂からの熱は作動流体(水またはガス)に伝達され、蒸気タービンを通過します。これらは船のプロペラを駆動したり、発電機のシャフトを回転させたりします。原子力で生成された蒸気は、原則として工業プロセス熱または地域暖房に使用できます。一部の原子炉は、医療用および産業用の同位体を製造したり、兵器級プルトニウムを製造したりするために使用されます。 2022 年の時点で、世界中で 422 基の発電炉と 223 基の研究炉が稼働していると国際原子力機関は報告しています。原子炉の初期の頃 (1940 年代)、原子炉は核パイルまたは原子パイルとして知られていました (臨界に達した最初の原子炉の黒鉛減速材ブロックが積み重ねられていたため、そう呼ばれました)。増加)。

学術論文

Self-welding of Inconel 617 under high-pressure-high-temperature conditions for nuclear reactors

..., 900–1000 °C), which, in conjunction with large load from subsystems/ components made of special heavy alloys, renders the reactor under the risk of self-welding, a phenomenon that could lead to strong bonding between components and paralyze the operability of the nuclear reactor.....

Angular momentum generation in nuclear fission.

...This insight into the role of spin in nuclear fission is not only important for the fundamental understanding and theoretical description of fission, but also has consequences for the γ-ray heating problem in nuclear reactors13,14, for the study of the structure of neutron-rich isotopes15,16, and for the synthesis and stability of super-heavy elements17,18.....

A new high-speed observation system for evaluating the spark location in WEDM of Inconel 718

...Wire electrical discharge machining (WEDM) is a good machining method for nickel-base superalloy, which is a key material in aero-engine, rocket engine and nuclear reactor.....

Tunable Chemical Disorder in Concentrated Alloys: Defect Physics and Radiation Performance.

...The development of advanced structural alloys with performance meeting the requirements of extreme environments in nuclear reactors has been long pursued.....

How to Operate a Nuclear Reactor

...The energy present in atomic nuclei can be harnessed either in an uncontrolled way in atomic bombs or in a controlled way in nuclear reactors.....

Effects of loss of heat sink transient on flow characteristics in a closed natural circulation system

...Two LOHS experiments (LOHS-1 and LOHS-2) were conducted in a well dimensioned closed loop NC test facility designed to represent the primary system of a nuclear reactor.....

A study of hydride precipitation in zirconium

...Zirconium-based alloys used in nuclear reactors are susceptible to hydrogen pickup.....

Overview of the Mechanical Properties of Tungsten/Steel Brazed Joints for the DEMO Fusion Reactor

...A Demonstration (DEMO) thermonuclear reactor is the next step after the International Thermonuclear Experimental Reactor (ITER).....

Uncertainty analysis in coupled neutronic/thermal-hydraulic calculations based on computational fluid dynamics

...There is an inevitable uncertainty in the coupled neutronic/thermal–hydraulic calculations, which are used for simulating the performance of nuclear reactors, due to the influence of design parameters and initial conditions.....

Generalized Perturbation Theory Based Total Sensitivity and Uncertainty Analysis for High-Fidelity Neutronics Calculation

...Neutronics calculation for nuclear reactor with high-fidelity technology can significantly reduce the uncertainties propagated from numerical approximation error and model error.....

The Phenomenon of a Natural Thermonuclear Reactor

...Herndon’s thesis about the existence of a thermonuclear reactor in the Earth’s core.....

Ab initio molecular dynamics assessment of thermodynamic and transport properties in (K,Li)Cl and (K, Na)Cl molten salt mixtures

...Molten salt mixtures are integral part of highly important technological applications such as nuclear reactors.....

Fire Safety Risk Analysis of Conventional Submarines

...This is because nuclear submarines are generally larger and are required to operate their nuclear reactors at all times, unlike diesel-electric submarines which are generally smaller and can run exclusively on batteries when submerged which generally requires fewer moving parts.....

Peelable coatings: A review

...Coupling the polymer chemistries, release agents with different additives can yield a broad spectrum of peelable coatings finding applications in decontamination of nuclear reactors, optics, automotive, floor coatings, electronic protection, food coatings, cosmetics and labels for plastics.....

Recent progress of radiation response in nanostructured tungsten for nuclear application

...Engineering materials for nuclear reactors exposed to high-dose irradiation breed various radiation damage, leading to performance degradation of materials, which seriously limits the application of materials in the future advanced nuclear reactors.....

Criticality Search of an Accelerator Driven System Using the ANET Code

...One of the most important safety parameters taken into consideration during the design and actual operation of a nuclear reactor is its control rods adjustment to reach criticality.....

Performance of radio-iodine discharge control methods of nuclear reprocessing plants.

...iodine-131 (131I) and iodine-129 (129I) are generated in considerable quantities in the nuclear fuel as fission products in the nuclear reactors.....

Quasi-Maxwellian Interference Term Functions

...It is a well-known fact that the physical processes taking place in nuclear reactors currently operating are addressed based on the Maxwell–Boltzmann distribution.....

The shielding properties of the ordinary concrete reinforced with innovative nano polymer particles containing PbO–H3BO3 for dual protection against gamma and neutron radiations

...Most of the neutron sources such as nuclear reactors and reaction based sources are considered as a mixed field of radiation where both of neutron and gamma particles are emitted directly from the source.....

Dynamic mode decomposition of numerical data in natural circulation

...Despite of its advantages, the application of the DMD methodology to investigate the natural circulation in nuclear reactors are very scarce in literature.....

Development of a PID-Fuzzy controller in the water level control of a pressurizer of a nuclear reactor

...A nuclear reactor has several systems that help keep it in normal operation, within safety margins.....

Heat transfer characterization under radial jet and falling film induced rewetting

...This kind of design to reflood the fuel bundle is different than bottom and top spray reflooding practiced in PWR and BWR type of nuclear reactors.....

Research on associated motion simulation method and platform of control rod driving mechanism

...Ensuring effective simulation accuracy is an important advance for accurately predicting the reliability of nuclear reactors.....

Prospects for the use of nanofluids in heating systems

...Such liquids can be considered as promising applications in such areas as solar collectors, heat pipes, nuclear reactors, electronic cooling systems, automobile radiators, etc.....

Development of Alternative Method for Manufacturing Structural Zirconium Elements for Nuclear Engineering

...Zirconium is used as a structural material for use in aggressive environments, including the core of nuclear reactors.....

Two-group phase distribution characteristics for air-water flow in 5 × 5 vertical rod bundle channel with mixing vane spacer grids

...The phase distribution in rod bundle channel was associated with the heat transfer coefficient, flow resistance and critical heat flux, which was of great significance for the design and safe operation of nuclear reactor and steam generator.....

Experimental Investigation of the Evolution of Fuel Clad Ballooning Using Real-Time X-ray Imaging and Its Microstructural Studies

...Clad ballooning, which is a plastic instability, results in sudden large deformation and thereby coolant flow blockage in case of transients in a nuclear reactor.....

Molecular dynamics simulation of the effect of temperature and size on the mechanical behavior of Cu50Zr50 metallic glass

...Because of their superior strength and corrosion resistance properties, metallic glasses can be used as structural materials in applications such as in nuclear reactors, marine vessels, etc.....

Sensor position optimization for flux mapping in a nuclear reactor using compressed sensing

...The paper presents a novel approach to sensor position optimisation based on compressed sensing (CS) and its application to neutron flux estimation in a nuclear reactor.....

Creep Properties of 9Cr and 14Cr ODS Tubes Tested by Inner Gas Pressure

...Oxide-dispersion strengthened steels are promising materials for extreme service conditions including nuclear reactors core.....

Increase in frequency of nuclear power outages due to changing climate

...Using operational data of nuclear reactors, Ali Ahmad identifies how disruptions in nuclear power production have increased over the years with increasing temperature anomalies, and projects future loss of output.....

Comparative study on the microstructure and mechanical properties of a modified 9Cr–2WVTa steel by normalizing-tempering and quenching-partitioning treatments

...Ferritic/martensitic (F/M) steels have been proposed as important candidates for structural materials of nuclear reactors due to their good mechanical properties and radiation resistance.....

Seismically Detecting Nuclear Reactor Operations Using a Power Spectral Density (PSD) Misfit Detector

...To explore the ability to indirectly detect and attribute various operations conducted at a nuclear reactor using waveform data, we investigated the seismic signals recorded near the High Flux Isotope Reactor (HFIR) located at Oak Ridge National Laboratory in Oak Ridge, Tennessee.....

Nuclear energy on the 21st century in climate limits context

...The article discusses the problem of the nuclear power system development in the variant of the coordinated use of fission reactors for energy production and hybrid thermonuclear reactors for production of artificial fuel from thorium raw materials for fission reactors.....

Giga-Cycle Fatigue Behavior of the Nuclear Structure of 316L Weldments

...Some components made of 316L stainless steel in nuclear reactors are connected by welding, and these are under giga-cycle fatigue loading.....

Magnetic Pulse Welding of D9 Steel Tube to SS316LN End Plug

...The integrity of the fuel clad plays a pivotal role in the performance and safety of a nuclear reactor.....

Heat transfer and pressure drop performance of Nanofluid: A state-of- the-art review

...solar thermal conversion systems, HVAC systems, electronic equipment, heat exchangers, nuclear reactors have imparted greater role in reducing negative impacts of climate change.....

Effect of Heat Treatment of a Liquid Alloy on Its Properties in the Molten State and after Amorphization

...Based on the earlier reported conceptions about the possibility to control the structure of liquid alloys by varying the heating temperature, we think that the use of optimized heat treatment of staring melts shows promise for stabilizing the properties of advanced liquid-metal coolants of nuclear reactors.....

手術

従来の火力発電所が化石燃料の燃焼によって放出される熱エネルギーを利用して発電するのと同じように、原子炉は、制御された核分裂によって放出されるエネルギーを熱エネルギーに変換し、さらに機械的に電気または電気の形に変換します。

= 核分裂 =

ウラン 235、ウラン 233、プルトニウム 239 などの大きな核分裂性核が中性子を吸収すると、核分裂が発生することがあります。重い原子核は 2 つ以上の軽い原子核 (核分裂生成物) に分裂し、運動エネルギー、ガンマ線、自由中性子を放出します。これらの中性子の一部は他の核分裂性原子に吸収され、さらなる核分裂現象を引き起こし、より多くの中性子を放出する可能性があります。これは核連鎖反応として知られています。 このような核連鎖反応を制御するには、中性子毒と中性子減速材を含む制御棒を使用して、さらなる核分裂を引き起こす中性子の割合を変更します。原子炉には通常、監視と計器が危険な状態を検出した場合に核分裂反応を停止する自動および手動システムが装備されています。

= 発熱 =

原子炉の炉心はさまざまな方法で熱を発生します。 核分裂生成物の運動エネルギーは、これらの核が近くの原子と衝突するときに熱エネルギーに変換されます。 原子炉は、核分裂中に生成されるガンマ線の一部を吸収し、そのエネルギーを熱に変換します。 熱は、核分裂生成物の放射性崩壊と中性子の吸収によって活性化された物質によって生成されます。この崩壊熱源は原子炉が停止した後もしばらく残ります。核プロセスによって変換される 1 キログラムのウラン 235 (U-235) は、従来の方法で燃焼される 1 キログラムの石炭 (7.2 × 1013) の約 300 万倍のエネルギーを放出します。 1 キログラムのウラン 235 が核分裂すると約 190 億キロカロリーが放出されるため、1 キログラムのウラン 235 が放出するエネルギーは燃焼によって放出されるエネルギーに相当します。石炭270万kg。

=冷却=

原子炉冷却材(通常は水ですが、場合によっては気体、液体金属(液体ナトリウムや鉛など)、溶融塩)が原子炉の炉心を循環し、発生する熱を吸収します。熱は反応器から運び去られ、蒸気の生成に使用されます。加圧水型原子炉などのほとんどの原子炉システムは、タービン用の加圧蒸気を生成するために沸騰水から物理的に分離された冷却システムを採用しています。しかし、一部の原子炉では、蒸気タービン用の水が炉心で直接沸騰させられます。たとえば沸騰水型原子炉。

= 反応性制御 =

=発電=

核分裂プロセスで放出されるエネルギーは熱を生成し、その一部は使用可能なエネルギーに変換できます。この熱エネルギーを利用する一般的な方法は、水を沸騰させて加圧蒸気を生成し、蒸気タービンを駆動してオルタネーターを回転させて発電することです。

= 生涯 =

原子力発電所は通常、平均寿命が 30 ~ 40 年になるように設計されています。適切に維持管理されていれば、原子力発電所は 80 年以上運転できると信じている人もいます。しかし、一部の重要部品、特に原子炉容器やコンクリート構造物は、中性子脆化や磨耗によって亀裂やひびが入った場合には交換できず、プラントの寿命が制限されます。計画された耐用年数が終了すると、プラントは操業ライセンスを約 20 年間延長できる場合があり、米国ではさらに 20 年間の「その後のライセンス更新」(SLR)を受ける資格もあります。たとえ認可が延長されたとしても、特に安全上の懸念や事故に直面した場合、原子炉が運転し続けることは保証されない。多くの原子炉は、ライセンスや設計寿命が切れるずっと前に閉鎖され、廃止されます。保存操作を継続するために必要な交換や改善のコストは法外に高額になる可能性があるため、費用対効果が高くありません。または、技術的な障害によりシャットダウンされる可能性があります。福島、スリーマイルズ島、セラフィールド、チェルノブイリなどの一部の施設は、地域の汚染のため閉鎖されている。たとえば、フランス企業 EDF Energy の英国支社は、最新型ガス冷却炉の運転寿命をわずか 3 ~ 10 年延長しました。 7 つの AGR プラントはすべて 2022 年に閉鎖され、2028 年までに廃止措置が開始される予定です。ヒンクリー ポイント B は 40 から 46 に延長され、閉鎖されました。 46年後、同じことがハンターストンBでも起こりました。 設計耐用年数が 30 年または 40 年に達するか、それを超える原子炉が増えています。グリーンピースは2014年、老朽化し​​た原子力発電所の寿命を延ばすことは新たなリスクの時代に突入することを意味すると警告した。報告書は、現在の欧州の原子力賠償責任補償範囲は、想定されるコストをカバーするには平均して100倍から1,000倍低すぎると推定しているが、同時に、拡大に伴い、欧州における重大事故の可能性は増大し続けている。年をとる。

初期の原子炉

== 核反応の種類別 ==

すべての商用発電炉は核分裂に基づいています。通常、核燃料としてウランとその生成物であるプルトニウムを使用しますが、トリウム燃料サイクルも可能です。核分裂炉は、核分裂連鎖反応を維持する中性子のエネルギーに応じて、大きく 2 つのクラスに分類できます。 熱中性子炉は、燃料の核分裂を維持するために減速中性子または熱中性子を使用します。現在のリアクトルはほぼすべてこのタイプです。これらには、中性子の温度が熱化されるまで、つまり中性子の運動エネルギーが周囲の粒子の平均運動エネルギーに近づくまで、中性子の速度を下げる中性子減速材が含まれています。熱中性子は、より高速な中性子と比較して、核分裂性核種のウラン 235、プルトニウム 239、およびプルトニウム 241 の核分裂断面積 (確率) がはるかに高く、ウラン 238 (U-238) による中性子捕獲の確率も高くなります。比較的低いです。核分裂でもともと発生する中性子を利用し、低濃縮ウランや天然ウラン燃料の利用が可能です。減速材は冷却剤でもあり、通常は沸点を上げるために高圧の水です。これらは、原子炉容器、原子炉を監視および制御するための機器、放射線遮蔽および格納容器によって囲まれています。 高速中性子炉は、高速中性子を使用して燃料の核分裂を引き起こします。これらは中性子減速材を持たず、減速度の低い冷却剤を使用します。連鎖反応を維持するには、U-238 による捕捉よりも核分裂の確率が比較的低いため、燃料中の核分裂性物質の濃度を高くする必要があります (約 20% 以上)。高速炉は、すべてのアクチニドが高速中性子で核分裂するため、超ウラン廃棄物の生成が少なくなる可能性がありますが、建設がより難しく、運転コストが高くなります。全体として、高速炉はほとんどの用途において熱反応器ほど一般的ではありません。初期の発電所の一部は高速炉であり、ロシア海軍の推進装置の一部も同様でした。原型炉の建設が進行中です(高速増殖炉または第 IV 世代炉を参照)。原理的には、核融合発電は、水素の重水素同位体などの元素の融合によって生成できます。少なくとも 1940 年代以来、豊富な研究が進行中ですが、いかなる目的の自己完結型核融合炉もこれまでに建設されたことはありません。

== 司会者による資料 ==

熱反応器で使用される: 黒鉛減速反応器 水減速炉 重水炉(カナダ、インド、アルゼンチン、中国、パキスタン、ルーマニア、韓国で使用)。 軽水炉 (LWR)。軽水炉 (最も一般的なタイプの熱原子炉) は、原子炉の減速と冷却に普通の水を使用します。水素同位体は軽度の中性子毒であるため、これらの原子炉には人工的に濃縮した燃料が必要です。動作温度では、水の温度が上昇すると密度が減少し、それを通過する中性子の数が減少し、さらなる反応を引き起こすのに十分な速度が低下します。負のフィードバックにより反応速度が安定します。黒鉛原子炉および重水炉は、軽水炉よりも完全に熱化される傾向があります。これらのタイプは追加の熱化や軽度の水素中毒の影響がなく、天然ウラン/非濃縮燃料を使用できます。 軽元素減速リアクター。 溶融塩炉 (MSR) は、冷却材/燃料マトリックス塩である LiF と BeF2、LiCl と BeCl2、およびその他の軽元素の構成成分であるリチウムやベリリウムなどの軽元素によって減速されます。含まれるすべての塩はリラックス効果をもたらします。 冷却剤が鉛とビスマスの混合物である液体金属冷却反応器では、減速剤として BeO を使用できます。 有機減速反応器 (OMR) は、減速剤および冷却剤としてビフェニルおよびテルフェニルを使用します。

== クーラントによる ==

水冷反応器。これらは稼働中の原子炉の大部分を占めています。 2014 年の時点で、世界の原子炉の 93% は水冷式であり、世界の原子力発電総容量の約 95% を占めています。加圧水型原子炉(PWR)が大部分を占めます。西側諸国のすべての原子力発電所の中で。 PWRの最大の特徴は、特殊な圧力容器である加圧器です。ほとんどの商用 PWR および海軍原子炉は加圧を使用します。通常の動作中、加圧器は部分的に水で満たされており、水中ヒーターで水を加熱することによって蒸気の泡がその上に維持されます。通常の運転中、加圧器は原子炉一次圧力容器(RPV)に接続されており、加圧器の「バブル」は原子炉内の水量の変化に対応するための膨張スペースを提供します。この構成は、加圧器ヒーターを使用して加圧器内の蒸気圧力を増加または減少させることによって反応器圧力を制御する手段も提供します。 加圧重水炉は加圧水型原子炉のサブセットであり、加圧された隔離された熱伝達ループの使用を共有しますが、中性子の経済性を高めるために冷却材および減速材として重水を使用します。増加。 沸騰水型原子炉 (BWR) BWR は、原子炉一次圧力容器の下部にある燃料棒の周囲で沸騰した水が発生するという特徴があります。沸騰水型原子炉は、二酸化ウランとして濃縮された 235U を燃料として使用します。燃料はロッドに組み立てられ、水中の鋼製容器に保管されます。核分裂により水が沸騰し、蒸気が発生します。この蒸気はパイプを通ってタービンに流れ込みます。タービンは蒸気によって駆動され、このプロセスにより電気が生成されます。通常の運転中、圧力は原子炉圧力容器からタービンに流れる蒸気の量によって制御されます。 超臨界水炉(SCWR) SCWR は第 4 世代原子炉のコンセプトであり、原子炉は超臨界圧力で動作し、水は超臨界流体に加熱され、蒸気に遷移することなく飽和蒸気のように動作し、蒸気発生器に供給されます。力を供給します。 還元減速水型原子炉 [RMWR] は、より高濃度の燃料を使用し、燃料要素を互いに近づけて配置することで、発熱中性子スペクトルとも呼ばれる、より高速な中性子スペクトルを実現します。 プール原子炉とは、非加圧水冷オープンプール原子炉を指しますが、ナトリウム冷却プール型 LMFBR と混同しないでください。 一部の原子炉は減速材としても機能する重水で冷却されています。例としては次のものが挙げられます。 初期の CANDU 原子炉 (後期のものは重水減速材を使用しますが、軽水冷却材を使用します) DIDO級研究炉 液体金属冷却反応器。水は減速材であるため、高速炉では冷却材として使用できません。液体金属冷却材には、ナトリウム、NaK、鉛、鉛ビスマス共融物、および初期の原子炉では水銀が含まれていました。 ナトリウム冷却高速炉 鉛冷却高速炉 ガス冷却反応器は循環ガスによって冷却されます。二酸化炭素は、英国の現在のAGR原子力発電所や、以前は英国、フランス、イタリア、日本の多くの第一世代原子力発電所などの商用原子力発電所で一般的に使用されています。私はそうでした。窒素とヘリウムも使用されますが、ヘリウムは高温設計に特に適していると考えられています。熱利用は反応器ごとに異なります。商用原子力発電所は、ガスを熱交換器に通して蒸気タービン用の蒸気を生成します。一部の実験設計では、ガスはガスタービンに直接電力を供給できるほど高温になります。 溶融塩反応器 (MSR) は、溶融塩 (通常は FLiBe などのフッ化物塩の共晶混合物) を循環させることによって冷却されます。典型的な MSR では、冷却剤は核分裂性物質を溶解するためのマトリックスとしても使用されます。使用される他の共晶塩の組み合わせには、「ZrF4」と「NaF」、「LiCl」と「BeCl2」などがあります。 有機反応器は、冷却剤として水の代わりにビフェニルやテルフェニルなどの有機流体を使用します。

== 世代別 ==

第 1 世代原子炉 (シッピングポート原子力発電所、研究用原子炉、非商用発電用原子炉などの初期のプロトタイプ) 第 2 世代原子炉 (現代の原子力発電所、1965 ~ 1996 年) 第 3 世代原子炉 (既存設計の進化的改良、1996 ~ 2016 年) 第 III 世代 + 原子炉 (第 III 世代原子炉の設計より安全な第 III 世代原子炉の進化的開発、2017 ~ 2021 年) 第 IV 世代原子炉 (技術はまだ開発中、開始日は不明、以下を参照) 第 V 世代の原子炉 (理論的には可能ですが、現在は設計が積極的に検討または研究されていません)。 2003 年、フランスのエネルギー・原子力委員会 (CEA) は、核電子工学の分野で「第 II 世代」タイプについて初めて言及しました。 「第 3 世代」について最初に言及されたのは 2000 年で、第 4 世代国際フォーラム (GIF) プロジェクトの立ち上げに関連して行われました。 「Gen IV」は、2000 年に米国エネルギー省 (DOE) によって、新しいタイプのプラントの開発のために命名されました。

== 燃料の段階別 ==

固形燃料 液体燃料 水系均一反応器 溶融塩炉 ガス燃料(理論上)

== コアの形状別 ==

立方体 円筒形 オクタゴン 球状 スラブ 環状

== 使用による ==

電気 小型モジュール型原子炉を含む原子力発電所 「推進」、「原子力推進」を参照 海洋原子力推進 さまざまなロケット推進システムを提案 熱のその他の利用 脱塩 家庭用および産業用暖房用の熱 水素経済で使用するための水素製造 元素変換用製造炉 増殖炉は、(肥沃な U-238 を Pu-239 に、または Th-232 を U-233 に変換することにより)核分裂連鎖反応中に消費するよりも多くの核分裂性物質を生成できます。増加。したがって、一旦稼働すると、ウラン増殖炉には天然ウランまたは劣化ウランを燃料補給することができ、トリウム増殖炉にはトリウムを燃料補給することができる。ただし、核分裂性物質の初期在庫が必要です。 煙探知機に使用されるアメリシウムや、画像処理や医療に使用されるコバルト 60 やモリブデン 99 など、さまざまな放射性同位体が生成されます。 兵器級プルトニウムおよびその他の核兵器用物質の生産 中性子源 (例: パルス式ゴディバ装置の使用) および陽電子源 (例: 中性子放射化分析およびカリウム - アルゴン年代測定) の提供 研究用原子炉: 通常、研究と訓練、材料試験、または医療用または産業用の放射性同位元素の製造に使用される原子炉。これらは発電炉や推進船よりもはるかに小さく、多くは大学のキャンパス内にあります。このような原子炉は約 280 基が 56 か国で稼働しています。一部は高濃縮ウラン燃料で運転しており、低濃縮ウラン燃料を代替する国際的な取り組みが進められている。

= 現在の技術 =

== 先進的原子炉 ==

開発のさまざまな段階で、数十の先進的な原子炉設計が存在します。上記の彼の一部は PWR、BWR、および PHWR 設計から発展しましたが、その他はより急進的な出発点です。前者には新型沸騰水型原子炉 (ABWR) が含まれており、そのうち 2 基は現在運転中であり、その他は建設中です。また、計画されている受動安全経済型単純沸騰水型原子炉 (ESBWR) および AP1000 ユニットも含まれています (原子力エネルギー 2010 計画を参照)。 統合高速炉(IFR)は 1980 年代に建設、試験、評価が行われ、核不拡散政策によりクリントン政権下の 1990 年代に廃止されました。使用済み燃料のリサイクルがその設計の中心であるため、現在の原子炉の廃棄物のほんの一部しか発生しません。 ペブルベッド炉、高温ガス冷却炉 (HTGCR) は、高温で燃料の中性子断面積がドップラー状になるように設計されており、出力が低下します。セラミック燃料を使用しているため、安全な動作温度は電力低下温度範囲を超えています。ほとんどの設計は不活性ヘリウムで冷却されます。ヘリウムは水蒸気爆発を通さず、放射性中性子の吸収に抵抗し、潜在的な放射性汚染物質を溶解しません。一般的な設計では、軽水炉(通常は 3 層)よりも多くの層(最大 7 層)の受動的格納容器を備えています。安全性を高める可能性のあるユニークな機能は、燃料ボールが実際にコア機構を形成し、経年劣化に応じて 1 つずつ交換されることです。燃料の設計により、燃料の再処理にコストがかかります。 小型密閉可搬型自律炉 (SSTAR) は主に米国で研究開発されており、受動的に安全であり、改ざんの疑いがある場合には遠隔から停止できる高速増殖炉として意図されています。 Clean and Environmentally Safe Advanced Reactor (CAESAR) は、減速材として蒸気を使用する原子炉のコンセプトであり、この設計はまだ開発中です。 還元減速水型原子炉は、現在使用されている新型沸騰水型原子炉 (ABWR) を基にして構築されていますが、主に熱中性子と高速中性子の中間の速度を持つ真の高速炉ではありません。発熱中性子を利用します。 水素減速自己制御核モジュール (HPM) は、ロスアラモス国立研究所によって開発された原子炉設計で、燃料として水素化ウランを使用します。 未臨界原子炉はより安全で安定するように設計されていますが、工学的および経済的に多くの課題を抱えています。一例はエネルギー増幅器です。 トリウムベースの原子炉 — 専用設計の原子炉でトリウム 232 を U-233 に変換することが可能です。このようにして、ウランの4倍豊富に存在するトリウムをU-233核燃料の増殖に使用することができます。また、U-233 は、伝統的に使用されてきた U-235 と比較して、中性子の経済性が高く、長寿命超ウラン廃棄物の生成が少ないなど、有利な核特性を備えていると言われています。考えられます 新型重水炉 (AHWR) — 提案されている重水減速炉であり、PHWR タイプの次世代設計です。インドのババ原子研究センター (BARC) で開発中。 KAMINI – 燃料にウラン 233 同位体を使用するユニークな原子炉。 BARC とインディラ・ガンジー核研究センター (IGCAR) によってインドに建設されました。 インドはまた、トリウム・ウラン233燃料サイクルを使用する高速増殖炉の建設を計画している。カルパカム(インド)で運転中のFBTR(高速増殖試験炉)は、​​燃料としてプルトニウム、冷却材として液体ナトリウムを使用している。 セロ・インパクト鉱床を管理する中国は原子炉を所有し、石炭を原子力エネルギーに置き換えたいと考えており、ロールス・ロイスは航空機用の合成燃料を生産するために原子炉を売却したいと考えている。

== 第 IV 世代の原子炉 ==

第 IV 世代原子炉は、一連の理論的な原子炉設計です。これらは一般的に 2040 年から 2050 年までに商用化されるとは予想されていないが、世界原子力協会は一部の原子炉が 2030 年までに商業運転に入る可能性があると示唆している。現在世界中で稼働している原子炉は、一般に第 2 世代または第 3 世代のシステムであると考えられています。第一世代のシステムはしばらく前に廃止されました。これらの原子炉タイプの研究は、8 つの技術目標に基づいて、第 4 世代国際フォーラム (GIF) によって正式に開始されました。主な目標は、原子力の安全性を向上させ、核拡散抵抗性を改善し、廃棄物と天然資源の利用を最小限に抑え、そのようなプラントの建設と運営のコストを削減することです。 ガス冷却高速炉 鉛冷却高速炉 溶融塩炉 ナトリウム冷却高速炉 超臨界水炉 超高温反応炉

== 第 V+ 世代の原子炉 ==

第 5 世代原子炉は理論的には可能な設計ですが、現在は積極的に検討または研究されていません。一部の第 5 世代原子炉は、現在または近い将来の技術を使用して建設される可能性がありますが、経済的、実用的、または安全性の理由からあまり関心がありません。 液体炉心炉。閉ループ液体炉心炉。核分裂性物質は、格納容器の底の穴からポンプで送られる作動ガスによって冷却された溶融ウランまたはウラン溶液です。 ガスコア炉。原子力電球ロケットの閉ループ型であり、核分裂性物質は溶融シリカ容器に入ったガス状六フッ化ウランです。作動ガス (水素など) がこの容器の周りを流れ、反応によって生成される UV 光を吸収します。この原子炉の設計は、ハリー・ハリソンの 1976 年の SF 小説『スカイフォール』に登場するように、ロケット エンジンとしても機能する可能性があります。理論的には、(現在行われているように段階的にではなく)UF6 を作動燃料として直接使用すると、処理コストが下がり、反応器がはるかに小さくなります。実際には、このような高出力密度で原子炉を運転すると、制御されない中性子束が生成され、ほとんどの原子炉材料が弱体化する可能性があります。したがって、中性子束は核融合炉で予想されるものと同様であるため、国際核融合炉用に選択されたものと同様の材料が必要となります。物質照射施設。 ガスコアEMリアクター。ガスコア炉と似ていますが、太陽電池アレイは紫外線を直接電気に変換します。このアプローチは、実験的に証明された光電効果に似ています。これは、高エネルギーの光子を導電性箔のアレイに通し、光子のエネルギーの一部を電子に伝達することにより、中性子を使わない核融合で生成された X 線を電気に変換します。コンデンサーと同様に静電気に捕らわれます。 X線は電子よりもはるかに厚い物質を通過できるため、X線を吸収するには何百または何千もの層が必要です。 核分裂デブリ炉。核分裂フラグメント炉は、核反応を利用して熱を発生させるのではなく、核分裂副産物のイオンビームを減速させることで発電する原子炉です。そうすることで、カルノー サイクルを回避でき、効率的なタービン駆動熱反応器で達成できる 40 ~ 45% の効率ではなく、最大 90% の効率を達成できます。核分裂フラグメントイオンビームは磁気流体力学発電機を通過して電気を生成します。 ハイブリッドフュージョン。核融合によって放出される中性子は、U-238 や Th-232 などの肥沃な物質を核分裂させたり、他の原子炉からの使用済み核燃料/核廃棄物を比較的良性の同位体に変換したりするために使用されます。増加。

== 核融合炉 ==

制御核融合は原理的にはアクチニドの取り扱いを複雑にすることなく核融合発電所で発電することができるが、重大な科学技術的障害が残っている。研究は 1950 年代に始まったものの、実用的な核融合炉は 2050 年までに完成するとは予想されていません。現在、ITER プロジェクトが核融合エネルギーの利用を主導しています。

核燃料サイクル

熱反応器は通常、精製および濃縮されたウランに依存しています。一部の原子炉はプルトニウムとウランの混合物で動作できます (MOX を参照)。ウラン鉱石が採掘、加工、濃縮、使用され、場合によっては再処理されて廃棄されるプロセスは、核燃料サイクルとして知られています。 天然ウランのうち核分裂性 U-235 同位体は 1% 未満であるため、ほとんどの原子炉設計では濃縮燃料が必要です。 濃縮には U-235 の割合を増やすことが含まれ、通常はガス拡散またはガス遠心分離によって行われます。濃縮された結果は二酸化ウラン粉末に変換され、圧縮されて焼成されてペレットになります。これらのペレットはチューブ内に積み重ねられ、その後密封され、燃料棒と呼ばれます。これらの燃料棒の多くは各原子炉で使用されます。 ほとんどの BWR および PWR 商業炉は、U-235 を約 4% 濃縮したウランを使用します。また、中性子の経済性が高い一部の商業炉は、燃料を濃縮する必要がまったくありません(つまり、天然ウランを使用できます)。国際原子力機関によると、高濃縮(兵器級/濃縮度90%)ウランを燃料とする研究用原子炉が世界に少なくとも100基ある。この燃料(核兵器の製造に使用される可能性がある)は盗まれる危険性があり、このタイプの原子炉を(拡散の脅威が少ない)低濃縮ウランに転換することを主張するキャンペーンにつながっている。増加。核分裂性 U-238 と非核分裂性 U-238 の両方が核分裂プロセスで使用されますが、核分裂性 U-235 と非核分裂性 U-238 の両方が使用されます。 U-235 は、熱中性子 (つまり、動きの遅い中性子) によって核分裂する可能性があります。熱中性子は、周囲の原子とほぼ同じ速度で移動する中性子です。すべての原子は絶対温度に比例して振動するため、熱中性子が同じ振動速度で移動しているときに U-235 が核分裂する可能性が最も高くなります。一方、中性子が非常に速く移動している場合、U-238 が中性子を捕捉する可能性が高くなります。この U-239 原子はすぐに崩壊して別の燃料であるプルトニウム 239 になります。 Pu-239 は実行可能な燃料であり、高濃縮ウラン燃料が使用される場合でも考慮する必要があります。一部の原子炉では、特に初期負荷の U-235 が使い果たされた後、プルトニウムの核分裂が U-235 の核分裂よりも優勢になります。プルトニウムは高速中性子と熱中性子の両方で非常に核分裂しやすいため、原子炉や核爆弾に最適です。 存在するほとんどの原子炉設計は熱原子炉であり、通常は中性子減速材(減速材とは中性子をその熱速度まで遅くすることを意味します)および冷却材として水を使用します。しかし、高速増殖炉では、中性子の速度をそれほど遅くしない、またはあまり遅くしない別のタイプの冷却材が使用されます。これにより、高速中性子が優勢になり、燃料供給を継続的に補充するために効果的に使用できます。安価な未濃縮ウランをそのような炉心に単に入れるだけで、非核分裂性のU-238が「増殖」燃料であるPu-239に変換される。 トリウム燃料サイクルでは、トリウム 232 が高速炉または熱炉で中性子を吸収します。トリウム 233 ベータはプロタクチニウム 233 に崩壊し、さらにウラン 233 に変化し、燃料として使用されます。したがって、ウラン 238 と同様に、トリウム 232 も肥沃な物質です。

= 原子炉への燃料供給 =

核燃料貯蔵庫内のエネルギー量は、多くの場合、「フルパワー日」という単位で表されます。これは、原子炉が熱を生成するためにフル出力で動作するようにスケジュールされている 24 時間期間 (日) の数です。エネルギー。原子炉運転サイクル (燃料交換停止中) の総出力日数は、サイクル開始時に燃料集合体に含まれる核分裂性ウラン 235 (U-235) の量に関係します。サイクル開始時の炉心内の U-235 の割合が高いほど、原子炉はフル出力でより長く運転できます。 原子炉内で 4 ~ 6 年間発電を行った後、運転サイクルの終わりには、一部の集合体の燃料が「使い果たされる」ことになります。この使用済み燃料は排出され、新しい(新しい)燃料集合体と置き換えられます。 「使用済み」とみなされますが、これらの燃料集合体には大量の燃料が含まれています。実際には、原子炉内の核燃料の寿命を決定するのは経済学です。核分裂が起こるずっと前に、原子炉は最大出力の 100% を維持できなくなるため、プラントの出力を下げると電力会社の収入が減少します。ほとんどの原子力発電所は、主に規制コストなどの運転諸経費のせいで、非常に低い利益率で運転されているため、100%未満の出力で運転することは、非常に長い間経済的に実行可能ではありません。ありえない。燃料交換中に交換される原子炉の燃料炉心の割合は通常 3 分の 1 ですが、燃料交換間のプラントの運転時間によって異なります。プラントは通常、18 か月の燃料補給サイクルまたは 24 か月の燃料補給サイクルで稼働します。これは、燃料の 3 分の 1 のみを交換する 1 回の燃料交換で、原子炉をほぼ 2 年間フル出力で維持できることを意味します。この使用済み燃料の処分と保管は、商業用原子力発電所の運転において最も困難な側面の 1 つです。この核廃棄物は放射性が高く、その毒性は数千年にわたって危険をもたらすでしょう。使用済み核燃料は原子炉から放出された後、敷地内の使用済み燃料プールに移送されます。使用済み燃料プールは、使用済み核燃料の冷却と遮蔽を提供する大きな水のプールです。ある程度のエネルギー減衰(約 5 年)後、燃料は燃料プールから乾燥したシールドキャスクに移され、そこで数千年間安全に保管できます。乾燥したシールドキャスクに積み込まれた後、キャスクは不浸透性のコンクリートバンカー内の特別に保護された施設に保管されます。敷地内の燃料貯蔵施設は、使用済み燃料へのダメージをほとんど与えずに旅客機の衝撃に耐えられるように設計されています。平均的な敷地内の燃料貯蔵施設は、サッカー場よりも小さなスペースで 30 年間の使用済み燃料を保管できます。燃料補給のためにすべての原子炉を停止する必要はない。たとえば、ペブルベッド反応器、RBMK 反応器、溶融塩反応器、マグノックス、AGR、および CANDU 反応器では、運転中に燃料が反応器内で移動できます。 CANDU 原子炉では、これにより、燃料要素内の U-235 の量に最適な炉心内に個々の燃料要素を配置することも可能になります。 核燃料から抽出されるエネルギー量は燃焼度と呼ばれ、燃料重量の初期単位当たりに生成される熱エネルギーで表されます。燃焼度は通常、初期重金属 1 トン当たりの熱量メガワット日として表されます。

原子力の安全性

原子力の安全性は、原子力および放射線の事故や事件の影響を防止または制限するために講じられる措置を対象としています。原子力産業は原子炉の安全性と性能を改善し、より安全な新しい原子炉設計を提案してきましたが(ただし、一般に試験は行われていません)、原子炉が正しく設計、建設、運転されるかどうかに対する懸念が高まっています。その保証はありません。間違いは必ず起こります。 NRG と日本の原子力安全局による度重なる警告にもかかわらず、日本の福島原子力発電所の原子炉の設計者は、地震後に原子炉を安定させるはずだったバックアップシステムが地震によって作動すると決定した。まさか津波で破壊されるとは思いませんでした。 。 UBS AGによると、福島第一原発の事故は、日本のような先進国ですら原子力の安全性を習得できるかどうかという疑問を引き起こしている。テロ攻撃を伴う壊滅的なシナリオも可能です。マサチューセッツ工科大学の学際的なチームは、2005 年から 2055 年までに予想される原子力の成長を考慮すると、その期間中に少なくとも 4 件の重大な原子力事故が発生すると予想されます。

原発事故

まれではありますが、重大な核事故や放射線事故が発生しています。これらには、風力スケール火災(1957 年 10 月)、SL-1 事故(1961 年)、スリーマイル島事故(1979 年)、チェルノブイリ事故(1986 年 4 月)、福島第一原子力発電所事故(2011 年)が含まれます。 2019年3月)が含まれます。原子力潜水艦事故には、K-19 原子炉事故(1961 年)、K-27 原子炉事故(1968 年)、K-431 原子炉事故(1985 年)などがあります。原子炉は少なくとも 34 回、地球周回軌道に打ち上げられています。多くの事故がソ連のRORSAT、特に無人原子炉を搭載したレーダー衛星コスモス954に関係し、その結果、核燃料が軌道から地球の大気圏に再突入し、カナダ北部に飛散した(1978年1月)。

天然原子炉

約20億年前、西アフリカのガボンにある現在オクロとして知られる地域で、一連の自立型核分裂「原子炉」が自己集合した。場所と時間の条件により、建設された原子炉内と同様の条件で自発的な核分裂が発生することが可能になりました。これまでのところ、ガボンのオクロラン鉱山の3つの別々の鉱床で15個の化石天然核分裂炉が発見されている。 1972 年にフランスの物理学者フランシス ペランによって初めて発見され、これらは総称してオクロ化石炉として知られています。これらの原子炉は約 15 億年前に自立核分裂反応を起こし、数十万年間稼働し、その間の平均出力は 100 kW でした。天然原子炉の概念は、アーカンソー大学のポール・クローダによって 1956 年にすでに理論化されていました。現在の地質時代では、そのような原子炉は地球上に形成できなくなります。以前は豊富であったウラン 235 が数億年かけて放射性崩壊した結果、この天然に存在する核分裂性同位体の割合は、水だけを減速材として連鎖反応を維持するのに必要な量まで減少しました。以下に減りました。 天然の原子炉は、ウランが豊富な鉱物鉱床に地下水が溢れ、中性子減速材として機能し、強力な連鎖反応を引き起こしたときに形成されました。反応が進むと水減速剤が沸騰し、反応が再び遅くなりメルトダウンが防止されます。核分裂反応は数十万年にわたって持続し、数時間から数日のオーダーで定期的に繰り返されました。 これらの天然原子炉は、地層放射性廃棄物処分に関心のある科学者によって広範囲に研究されてきました。これらは、放射性同位体が地殻中をどのように移動するかについてのケーススタディを提供します。地層廃棄物処分に反対する人々は、保管されている廃棄物からの同位体が水道や環境に流入する可能性を懸念しているため、これは重要な論争の分野となっている。 。

排出量

原子炉は通常の運転の一環としてトリチウムを生成し、最終的には微量のトリチウムを環境中に放出します。 水素の同位体であるトリチウム (T) は、頻繁に酸素と結合して T2O を形成します。この分子は化学的に H2O と同一であるため、無色無臭ですが、水素原子核内に追加の中性子が存在すると、トリチウムは 12.3 年の半減期でベータ崩壊を起こします。原子力発電所からのトリチウムの排出は、測定可能ではありますが、最小限です。米国NRCは、重大なトリチウム水流出と考えられるもので汚染された井戸の水を1年間飲んだ人は0.3ミリレムの放射線量を受けると推定している。比較のために言うと、これはワシントン D.C. からロサンゼルスまでの往復の飛行機で人が受ける 4 ミリレムよりも一桁小さく、高高度での高エネルギー宇宙線に対する大気保護が不十分な結果です。 。通常運転中の原子力発電所から放出されるストロンチウムの量は非常に少ないため、自然バックグラウンド放射線を超えて検出することはできません。地下水および一般環境から検出可能なストロンチウム 90 は、20 世紀半ばの兵器実験 (環境中のストロンチウム 90 の 99% を占める) とチェルノブイリ事故 (残りの 1% を占める) にまで遡ることができます。 。 )。

外部リンク

原子力発電炉に関するデータベース – IAEA ウラン会議が日本の事故についての議論を追加 討論: 原子力発電は地球温暖化の解決策ですか? 懸念科学者連合、米国の原子炉計画に関する懸念 Freeview ビデオ「原子力発電所 — 問題は何ですか」ベガ サイエンス トラストによるジョン コリアーによる王立施設での講義。 原子力エネルギー研究所—仕組み: 発電 原子炉技術の注釈付き参考文献 (Alsos デジタル ライブラリから) ソ連における宇宙炉の開発と応用

原子力発電所

学術論文

Who is willing to participate? Examining public participation intention concerning decommissioning of nuclear power plants in Belgium

...Decommissioning of Nuclear Power Plants (NPPs) is now a pertinent energy-related matter since most of the nuclear reactors built during nuclear renaissance will soon reach the end of their operational life.....

Моделювання теплових процесів парогенератора АЕС для інформаційної технології оптимізації управління

...Mathematical models of thermal processes in the form of Cauchy in the state space with relative variables of the steam generator PGV-1000 of the power unit of a nuclear power plant with a nuclear reactor VVER-1000 have been developed for the using of models in information technology for optimizing the control of a steam generator.....

RDE Design Strategy for Indonesia Experimental NPP

...The main goal of initiating the RDE design Program, beside developing the national capability as a nuclear reactor technology provider by mastering the design, construction project management, commissioning and operation of a nuclear power reactor, is to mastering nuclear power plant that to be able to be scaled-up and commercialized to support the national energy security.....

The probability of the existence of defects that lead to the destruction of the pressure vessel without leak

...To ensure the safety of a nuclear power plant on the basis of the requirements of norms and rules in the field of the use of atomic energy for pipelines of the primary circuit of a nuclear reactor, the design should apply the leak before break concept.....

Time-dependent reliability analysis of the reactor building of a nuclear power plant for accounting of its aging and degradation

...The ultimate barrier to prevent contamination of the environment due to a release of radioactivity from a Nuclear Power Plant (NPP) is the reinforced concrete (RC) Reactor Building (RB) which encloses the nuclear reactor.....

A rapid coupling method for calculating the radiation field in decommissioning nuclear power plants

...This paper establishes a nuclear power plant model and uses the nuclear reactor's available power operation history to calculate device source data.....

GIS-based multi-criteria analysis for nuclear power plant site selection in West Kalimantan

...Nuclear power is set as the highest priority to slow global warming, so the construction of a nuclear power plant (NPP) using nuclear reactors as a source of heat energy is initiated to produce pollution-free electricity.....

Computing and Information Technologies in the Nuclear Industry

...Methods of mathematical modeling are widely used in the design of nuclear reactors; the study of the properties of materials, including their radiation resistance; the study of nuclear safety issues; and the design of nuclear power plants.....

CFD study on crossflow and heat transfer characteristics of single phase flow in rod bundle with spacer grid under rolling conditions

...In order to study the thermal and hydraulic characteristics of nuclear reactors under ocean conditions and meet the urgent needs of the design of floating nuclear power plants, the crossflow and heat transfer characteristics of rod bundle with the spacer grid under rolling conditions are studied by using computational fluid dynamics (CFD) code.....

Study Protocol for radiation exposure and cancer risk assessment- The Taiwan Nuclear Power Plants and Epidemiology Cohort Study (TNPECS).

...BACKGROUND This cohort was established to evaluate whether 38-year radiation exposure (since the start of nuclear reactor operations) is related to cancer risk in residents near three near nuclear power plants (NPPs).....

HOW TO ISOLATE RADIONUCLIDES? ON THE ELECTROCHEMICAL PURIFICATION OF TECHNOLOGICAL EQUIPMENT FROM RADIONUCLIDE CONTAMINATION — DEVELOPMENT BY CHEMISTS OF THE ACADEMY

...The method was successfully tested at the Chornobyl nuclear power plant and on the Research Nuclear Reactor of the Institute of Nuclear Research of the National Academy of Sciences of Ukraine.....

Nuclear reactor vessel water level prediction during severe accidents using deep neural networks

...Acquiring instrumentation signals generated from nuclear power plants (NPPs) is essential to maintain nuclear reactor integrity or to mitigate an abnormal state under normal operating conditions or severe accident circumstances.....

パッシブセーフティシステム

学術論文

Computational fluid dynamics analysis of buoyancy-aided turbulent mixed convection inside a heated vertical rectangular duct

...Heat transfer can occur in the passive safety system of a nuclear reactor, which uses natural circulation as an initial driving force owing to its relatively low flow rate and strong heat flux condition.....

Application of adjoint-based sensitivity analysis to natural circulation of high-Pr fluid inside heat transport system

...Various passive safety systems have been developed for advanced nuclear reactors.....

Experimental research on double-hole steam condensation effects and models under different diameters and pitch to diameter ratios conditions

...The multi-hole steam Direct Contact Condensation (DCC) is of high efficiency in mass and heat transfer, which has been widely used in the engineering application, especially the advanced nuclear reactor power plant passive safety system.....

INVESTIGATION OF A SELF-ACTUATED, GRAVITY-DRIVEN SHUTDOWN SYSTEM IN A SMALL LEAD-COOLED REACTOR

...Passive safety systems in a nuclear reactor allow to simplify the overall plant design, beside improving economics and reliability, which are considered to be among the salient goals of advanced Generation IV reactors.....

Experimental Study of Thermal Behavior of a Single-phase Natural Circulation Loop with Vertical Heater and Cooler

...This study is expected to be one of the references to the design of a single-phase natural circulation loop as an advanced nuclear reactor passive safety system.....

Behavior of an air-cooled thermosiphon during a non-air gas ingress event

...Results presented are from experimental testing conducted on a large-scale thermal hydraulic facility that examines heat removal performance of the Reactor Cavity Cooling System (RCCS) concept, a passive safety system for advanced nuclear reactors.....

Local flow structure and turbulence quantities inside a heated rectangular riser in turbulent forced and mixed convection heat transfers

...The reactor cavity cooling system (RCCS), a passive safety system in a very high temperature gas-cooled nuclear reactor (VHTR), incorporates rectangular riser channels to remove residual heat emitted from the reactor vessel, where turbulent mixed convection may occur under some emergency operation conditions.....

Comparative Analysis of Thermal Hydraulic Parameters of AP-1000 and VVER-1200 Nuclear Reactor for Turbine Trip Concurrent with Anticipated Transient Without SCRAM (ATWS)

...Generation III+ type nuclear reactors have highly reliable active and passive safety systems with some inherent safety characteristics for attaining proper operating conditions, preventing any chance of accidents, or minimizing after-effects if any accident occurs to ensure that workers, the public and the environment are safe from undue radiation hazards.....

Indirect validation of fluid-to-fluid scaling criteria for modeling steam condensation based on empirical correlations and CFD simulations

...Several nuclear reactor designs have adopted passive safety systems with condensation inside horizontal tubes, such as the Passive Auxiliary Feedwater System (PAFS) of the APR+, the new generation of the Korean-Standard Pressurized Water Reactors (PWR).....

原子炉圧力容器

学術論文

Investigation of DPA in the reactor pressure vessel of VVER-1000/V320

...The most important ageing effect on the reactor pressure vessel (RPV) is radiationembrittlement, which is mainly caused by fast neutrons during operation lifetime of nuclear reactors.....

MD Simulation of Hundred-Billion-Metal-Atom Cascade Collision on Sunway Taihulight

...Radiation damage to the steel material of reactor pressure vessels is a major threat to the nuclear reactor safety.....

CFD simulation on the transient process of coolant mixing phenomenon in reactor pressure vessel

...The emergency coolant cooling system (ECCS) is designed to inject coolant into reactor pressure vessel (RPV) during loss of coolant accidents, ensuring the sufficient coolant inventory in the nuclear reactor core.....

Thermo-mechanical behavior of an ablated reactor pressure vessel wall in a Nordic BWR under in-vessel core melt retention

...The reactor pressure vessel (RPV) of a nuclear reactor is one of the key safety barriers preventing radioactive environmental releases during a severe accident.....

Precipitation in reactor pressure vessel steels under ion and neutron irradiation: On the role of segregated network dislocations

...The ultrahigh density of Mn-Ni-Si-Cu precipitates that form in irradiated reactor pressure vessels (RPV) result in hardening and embrittlement, which may limit the service life of aging nuclear reactors.....

Scaling analysis of the hydraulic behavior in reactor pressure vessel

...The hydraulic behavior of coolant flow in reactor pressure vessel plays an important role in the thermal hydraulic and safety analysis of nuclear reactor system.....

Failure behaviour of cladding made from Sv 07Kh25N13 austenitic stainless steel

...Due to its excellent corrosion resistance in the environment of WWER type nuclear reactor primary circuit, it is applied as anticorrosive cladding of the reactor pressure vessel.....

二相流

学術論文

Interfacial area concentration in gas-liquid metal two-phase flow

...The characterization and modelling of the flow features in gas and heavy liquid metal two-phase flow are required for the development of next generation nuclear reactor systems.....

The effect of surfactant concentrations and surface material on heat transfer coefficient in nucleate boiling regime

...The nucleate boiling regime and two-phase flow are greater importance to the safety analysis of nuclear reactors.....

GPU Acceleration of Multigrid Preconditioned Conjugate Gradient Solver on Block-Structured Cartesian Grid

...The numerical experiments are conducted for two-phase flows in a fuel bundle of a nuclear reactor.....

Experimental investigation on flow oscillation of boiling two-phase flow in a single rod channel

...Flow oscillation of two-phase flow has significant effect on the safety of relative industrial application, such as nuclear reactor.....

燃料被覆材

学術論文

Coupled Thermomechanical Responses of Zirconium Alloy System Claddings under Neutron Irradiation

...Zirconium (Zr) alloy is a promising fuel cladding material used widely in nuclear reactors.....

Irradiation Hardening and Microstructure Characterization of Zr -1% Nb During Low Dose Neutron Irradiation

...Due to low neutron absorption cross section, high mechanical strength, high thermal conductivity and good corrosion resistance in water and steam, Zirconium alloys are widely used as fuel cladding material in nuclear reactors.....

Reversible phase transformation in Ti2AlC films during He radiation and subsequent annealing

...Ti2AlC film can be used as a protective coating for fuel cladding materials and structural materials in nuclear reactors.....

Ultra-fine-grained and gradient FeCrAl alloys with outstanding work hardening capability

...FeCrAl alloy is a promising accident tolerant fuel cladding material for next generation nuclear reactors.....

熱中性子束

学術論文

Improvements in Quality of Neutron Radiography Images of Pyro Components Used in Aerospace Applications Using Image Processing Tools

...Since the thermal neutron flux available for NR using above sources (in an enclosure based set up) is very low (104 n/cm2 s), the quality of the neutron images is less in comparison to NR images obtained from setups that use nuclear reactor as neutron source (107 n/cm2 s).....

Efficiency limitation of thin film coated planar semiconductor thermal neutron detector.

...Semiconductor thermal neutron detectors are increasingly been used in in-core thermal neutron flux measurements in nuclear reactors.....

3He proportional counter development for thermal neutron detection

...This last characteristic has ensured that this detector is one of the best tools for thermal neutron flux measurements in a nuclear reactor control.....

多群中性子拡散

学術論文

Virtual element methods for the spatial discretisation of the multigroup neutron diffusion equation on polygonal meshes with applications to nuclear reactor physics

...This paper presents the first application of VEM to the field of nuclear reactor physics, specifically to the steady-state, multigroup, neutron diffusion equation (NDE).....

MATLAB PDE toolbox for 2-D and 3-D neutron diffusion simulations

...This research extends MATLAB PDE Toolbox to model nuclear reactors by solving the 2-D and 3-D multigroup neutron diffusion equations using the finite element method.....

Solution of the Multigroup Neutron Diffusion Eigenvalue Problem in Slab Geometry by Modified Power Method

...We describe in this work the application of the modified power method for solve the multigroup neutron diffusion eigenvalue problem in slab geometry considering two-dimensions for nuclear reactor global calculations.....

熱エネルギー貯蔵

学術論文

Natural Convection Heat Transfer Enhancement of Circular Obstacle within Square Enclosure

...The natural convection heat transfer within the enclosure is a classical problem by highlighting the real field applications such as electronic packaging industry, PCR-chips for DNA amplification, energy-efficient design of buildings rooms, operation and safety of nuclear reactors, convective heat transfer within boilers, furnaces and solar systems and thermal energy storage.....

Experimental investigation of turbulent characteristics in pore-scale regions of porous media

...The study of flow dynamics in porous media or randomly packed beds is essential because these systems are commonly applied in a wide array of engineering applications, such as thermal energy storage, catalytic reactors for processing and distillation, oil recovery, fuel cells, and pebble bed nuclear reactor cores.....

Comparative Studies of the Structural and Transport Properties of Molten Salt FLiNaK Using the Machine-Learned Neural Network and Reparametrized Classical Forcefields.

...This work demonstrated a computational framework that can facilitate the screening of molten salts with different chemical compositions, impurities, and additives, and at different thermodynamic conditions suitable for the next-generation nuclear reactors and thermal energy storage facilities.....

核燃料被覆管

学術論文

Safely probing the chemistry of Chernobyl nuclear fuel using micro-focus X-ray analysis

...A fascinating mixture of molten UO2, nuclear fuel cladding, concrete, stainless steel and other nuclear reactor components, these materials behaved like lava, solidifying to form a complex, highly radioactive glass-ceramic.....

Hydride growth mechanism in zircaloy-4: Investigation of the partitioning of alloying elements

...The long-term safety of water-based nuclear reactors relies in part on the reliability of zirconium-based nuclear fuel cladding.....

Oxidation-resistant coating of FeCrAl on Zr-alloy tubes using 3D printing direct energy deposition

...Zr-alloys are used as nuclear fuel cladding tubes in nuclear reactors.....

応力腐食割れ

学術論文

Emergence of micro-galvanic corrosion in plastically deformed austenitic stainless steels

...Localized plastic deformation has been observed to render nuclear reactor components more susceptible to stress corrosion cracking (SCC).....

Long-term initiation time for stress -corrosion cracking of alloy 600 with implications in stainless steel: Review and analysis for nuclear application

...This paper provides a summary and analysis on the initiation of stress -corrosion cracking (SCC) of Alloy 600 (and related alloys) and stainless steels in nuclear reactor environments near 300 °C.....

Post-Irradiation Analysis of Additively Manufactured Stainless Steel 316L Specimens

...Nuclear reactor materials are known to be susceptible to hardening and embrittlement, irradiation-assisted stress corrosion cracking, and void swelling when exposed to high temperature radiation fields for long periods of time (Was and Andresen, 2012).....

中性子輸送方程式

学術論文

Numerical analysis of the neutron multigroup SP N equations

...The multigroup neutron SPN equations, which are an approximation of the neutron transport equation, are used to model nuclear reactor cores.....

Numerical Approximation for Fractional Neutron Transport Equation

...Fractional neutron transport equation reflects the anomalous transport processes in nuclear reactor.....

ADAPTIVE SOLUTION OF THE NEUTRON DIFFUSION EQUATION WITH HETEROGENEOUS COEFFICIENTS USING THE MIXED FINITE ELEMENT METHOD ON STRUCTURED MESHES

...The neutron transport equation can be used to model the physics of the nuclear reactor core.....

液体金属高速

学術論文

In situ Monitoring of the Oxidation of Coated and Uncoated Austenitic Stainless Steels at Temperatures Lower than 600 °C: Part A—Coating Screening

...The lithium niobate used in an ultrasonic transducer for liquid metal fast nuclear reactors is prone to a reduction leading to a rapid short circuit of the sensor in operating conditions.....

Fluid-structure interaction of a 7-rods bundle: Benchmarking numerical simulations with experimental data

...Fluid flows through rod bundles are observed in many nuclear applications, such as in the core of Gen IV liquid metal fast breeder nuclear reactors (LMFBR).....

温度ガス冷却

学術論文

Overview of high temperature gas-cooled reactor

...A high temperature gas-cooled reactor (HTGR) is a nuclear reactor that can supply high temperature heat energy of 750°C–950°C by using a spherical fuel coated with ceramics such as carbon and silicon carbide, inert helium gas as a coolant, and graphite as a moderator.....

Cardinal: A Lower-Length-Scale Multiphysics Simulator for Pebble-Bed Reactors

...The FHR is a class of advanced nuclear reactors that combines the robust coated particle fuel form from high-temperature gas-cooled reactors, the direct reactor auxiliary cooling system passive decay removal of liquid-metal fast reactors, and the transparent, high-volumetric heat capacitance liquid-fluoride salt working fluids (e.....

高度な原子炉

学術論文

Multi-criteria comparison of nuclear reactors using the MULTIMOORA method: A case of study for Chile

...Our task was to develop an extension of the Multi-Objective Optimization by Ratio Analysis (MULTIMOORA) for advanced nuclear reactor prioritization in developing countries.....

Comparative studies of iterative methods for solving the “optimally diffusive” coarse mesh finite difference accelerated transport equation

...The emergence of advanced nuclear reactor systems with increasing complexity and heterogeneity has necessitated detailed high fidelity neutronic analysis.....

Application of adjoint-based sensitivity analysis to natural circulation of high-Pr fluid inside heat transport system

...Various passive safety systems have been developed for advanced nuclear reactors.....

A HIGH-FIDELITY SIMULATION OF THE C5G7 BENCHMARK BY USING THE PARALLEL ENTER CODE

...In simulation of advanced nuclear reactors, requirements like high precision, high efficiency and convenient to multi-physics coupling are putting forward.....

Experimental research on double-hole steam condensation effects and models under different diameters and pitch to diameter ratios conditions

...The multi-hole steam Direct Contact Condensation (DCC) is of high efficiency in mass and heat transfer, which has been widely used in the engineering application, especially the advanced nuclear reactor power plant passive safety system.....

Predicting structural material degradation in advanced nuclear reactors with ion irradiation

...Swelling associated with the formation and growth of cavities is among the most damaging of radiation-induced degradation modes for structural materials in advanced nuclear reactor concepts.....

Fate and transport of unruptured tri-structural isotropic (TRISO) fuel particles in the event of environmental release for advanced and micro reactor applications.

...Advanced nuclear reactor designs and advanced fuel types offer safety features that may reduce environmental consequences in an accident scenario when compared to conventional reactors and fuels.....

Small Modular and Advanced Nuclear Reactors: A Reality Check

...Small modular and advanced nuclear reactors have been proposed as potential ways of dealing with the problems—specifically economic competitiveness, risk of accidents, link to proliferation and production of waste—confronting nuclear power technology.....

Elevated-Temperature Elastic Properties of Alloys 709 and 617 Measured by Laser Ultrasound

...These alloys are of interest for structural applications in advanced nuclear reactors.....

Does the pathway for development of next generation nuclear materials straightly go through high-entropy materials?

...The concept of entropy stabilized complex materials provides a novel direction for the design and engineering of breakthrough materials to be used in extreme environments and particularly in advanced nuclear reactors.....

Temperature-Dependent Properties of Molten Li2BeF4 Salt Using Ab Initio Molecular Dynamics

...Molten lithium tetrafluoroberyllate (Li2BeF4) salt, also known as FLiBe, with a 2:1 mixture of LiF and BeF2 is being proposed as a coolant and solvent in advanced nuclear reactor designs, such as the molten salt reactor or the fluoride salt cooled high-temperature reactor.....

Metallic Fast Reactor Separate Effect Studies for Fuel Safety

...Sodium-cooled Fast Reactors (SFR) are one of the advanced nuclear reactor concepts to be commercially applied for electricity production.....

High-throughput ion irradiation of additively manufactured compositionally complex alloys

...Several advanced nuclear reactor designs promise efficiency and safety improvements over the current reactor fleet but are limited by the current set of ASME code-qualified materials.....

Determination of lattice physics properties and uncertainties in a solid fuel molten salt cooled assembly using OpenMC

...The desire for reducing our carbon footprint is driving significant interest in advanced nuclear reactors to produce energy.....

An Investigation of Speech Features, Plant System Alarms, and Operator–System Interaction for the Classification of Operator Cognitive Workload During Dynamic Work

...Method The study was conducted in a full-scope control room research simulator of an advanced nuclear reactor.....

Enhanced self-healing of irradiation defects near a Ni–graphene interface by damaged graphene: Insights from atomistic modeling

...Graphene-reinforced nickel matrix nanocomposites with high-density interfaces are recommended as candidate materials for advanced nuclear reactors because of the potential irradiation tolerance.....

Dynamic observation of dual-beam irradiated Fe and Fe-10Cr alloys at 435 °C

...The attractive mechanical properties and superior resistance to void-swelling make ferritic/martensitic alloys a promising structural material for advanced nuclear reactors.....

Response of nanoclusters to heavy-ion irradiation in an Fe-12Cr ODS steel

...Oxide dispersion-strengthened (ODS) steel is one of the most prominent candidates as the fuel cladding or blanket component in advanced nuclear reactors.....

Cardinal: A Lower-Length-Scale Multiphysics Simulator for Pebble-Bed Reactors

...The FHR is a class of advanced nuclear reactors that combines the robust coated particle fuel form from high-temperature gas-cooled reactors, the direct reactor auxiliary cooling system passive decay removal of liquid-metal fast reactors, and the transparent, high-volumetric heat capacitance liquid-fluoride salt working fluids (e.....

Current development of body-centered cubic high-entropy alloys for nuclear applications

...High-entropy alloys with body-centered cubic (BCC) structures, especially refractory high-entropy alloys, are considered as promising materials for high-temperature applications in advanced nuclear reactors.....

High-resolution high-speed void fraction measurements in helically coiled tubes using X-ray radiography

...However, in most of the steam generator designs adopted in advanced nuclear reactors, the two-phase mixture flows upward within the vertically oriented helical coils.....

Nano-amorphous layers improve the helium swelling resistance of a CAC-type nanocomposite

...This result sheds light on the design of radiation-tolerant materials for advanced nuclear reactor applications.....

Neutronic Performances of 100 MWe MSR with Weapon Grade Plutonium Fuel

...An advanced nuclear reactor Generation IV, called Molten Salt Reactor (MSR), has been developed with Thorium utilization for a sustainable energy system.....

Experimental Study of Thermal Behavior of a Single-phase Natural Circulation Loop with Vertical Heater and Cooler

...This study is expected to be one of the references to the design of a single-phase natural circulation loop as an advanced nuclear reactor passive safety system.....

Nuclear data evaluation augmented by machine learning

...Both models were used to predict nuclear data for 233 U , a well-characterized isotope in literature, and 35 Cl , a less studied but important nuclide for some advanced nuclear reactors.....

Machine Learning-Based Methodology for Assessment of Doppler Reactivity of Sodium-Cooled Fast Reactor

...In order to close nuclear fuel cycle and address the problem of sustainability, advanced nuclear reactor systems of the fourth generation are in the focus of the research for many years.....

Ultrafine intralath precipitation of V(C,N) in 12Cr-1MoWV (wt.%) ferritic/martensitic steel

...%) ferritic/martensitic (F/M) steel is a candidate material for fuel cladding in advanced nuclear reactors.....

Behavior of an air-cooled thermosiphon during a non-air gas ingress event

...Results presented are from experimental testing conducted on a large-scale thermal hydraulic facility that examines heat removal performance of the Reactor Cavity Cooling System (RCCS) concept, a passive safety system for advanced nuclear reactors.....

Reducing Anisotropy in High Yttria Ferritic Oxide Dispersion Strengthened Steels by Powder Forging

...Oxide dispersion strengthened (ODS) steels are being developed for fuel claddings in advanced nuclear reactors.....

Experimental study of steam and steam–air mixture condensation over vertical chrome-plated tube and polished tube exterior surface

...In this article, a series of steam condensation experiments were performed on the outer surface of chrome-plated tube and polished tube under steam and steam–air mixed conditions to study their heat transfer characteristics and whether they could be used to optimize Passive Containment Cooling System in advanced nuclear reactors.....

In situ TEM investigations of the microstructural changes and radiation tolerance in SiC nanowhiskers irradiated with He ions at high temperatures

...The large surface area to volume ratio enhances defect recombination supressing the defect density in the SiC NWs compared to the foils indicating high radiation tolerance; however, elemental segregation and precipitation may limit its application in advanced nuclear reactors.....

Role of zirconium in neodymium-dopants interactions within uranium-based metallic fuels

...Metallic fuels proposed for advanced nuclear reactors are found to be superior to other fuel types in terms of high thermal conductivity, proliferation resistance, excellent compatibility with the sodium coolant, and in some configurations inherent safety.....

An integrated experimental and computational investigation of defect and microstructural effects on thermal transport in thorium dioxide

...Advanced nuclear reactor concepts aim to use fuels that must withstand unprecedented temperature and radiation extremes.....

Revealing the chemical environment of Cr, Fe, and Ni in high temperature-ultrafine precipitate strengthened steel subjected to low fluence neutron irradiation

...High temperature-ultrafine precipitate strengthened (HT-UPS) steel has potential applications in advanced nuclear reactors as a structural material.....

THERMAL SCATTERING LAW ENDF LIBRARIES FOR LIQUID FLIBE

...Several advanced nuclear reactor concepts have been proposed in the past few years where FLiBe molten salt represents a major constituent of the core.....

A quasi-3D direct transport method in the direct transport code KuaFu

...The 2D/1D transport method is suffered from the stability issues, which affects the application in direct whole-core transport calculation for advanced nuclear reactors.....

RE-EVALUATION OF THE TSL FOR YTTRIUM HYDRIDE

...Yttrium hydride (YHx) is of interest as a high-temperature moderator material in advanced nuclear reactor systems because of its superior ability to retain hydrogen at elevated temperatures.....

冷却原子炉

学術論文

Influence of displacement rate and temperature on the severity of liquid metal embrittlement of T91 steel in LBE

...The fracture toughness values in LBE were found to be very low to support the selection of T91 material for the LBE cooled nuclear reactors.....

Physical Phenomena in Nuclear Thermal Hydraulics and Current Status

...The derived T-HP list includes consideration of experiments performed in Separate Effect Test (SET) and Integral Effect Test (IET) facilities relevant to reactor coolant system and containment of Water Cooled Nuclear Reactors (WCNR).....

Role of surface diffusion in formation of unique reactivity for graphite oxidation: Time-resolved measurements in a pulsed diffusion reactor

...Quantification of oxidation kinetics is essential to develop graphitic materials for diverse applications: from refractories found in gas-cooled nuclear reactors to catalysts needed for chemical manufacturing.....

Evolution of a low-alloy steel/nickel superalloy dissimilar metal weld during post-weld heat treatment

...The design of the dissimilar metal weld investigated here is aimed at applications in the steam generator of a sodium-cooled nuclear reactor, with a multi-decade lifespan in demanding operational conditions.....

CO2 power cycle chemistry in the CV Řež experimental loop

...The inspiration for the proposal of these systems could stem from the gas, especially the CO2-cooled nuclear reactors operation.....

Influence of thermal expansion bend and tubesheet geometry on guided wave inspection of steam generator tubes of a fast breeder reactor

...Periodic assessment of steam generator tubes of a sodium-cooled nuclear reactor is very crucial for smooth operation of steam generators.....

Study on adaptive heat transfer performance of high temperature heat pipe

...Due to the large latent heat of its working fluid during phase change heat transfer, HTHP has the advantages of high temperature uniformity, high working temperature and high intensity heat transfer capacity, which has broad application prospects in the field of HTHP cooled nuclear reactors and the thermal protection of hypersonic vehicles.....

An old issue and a new challenge for nuclear reactor safety

...Nuclear reactor safety (NRS) and the branch accident analysis (AA) constitute proven technologies: these are based on, among the other things, long lasting research and operational experience in the area of water cooled nuclear reactors (WCNR).....

Modelling reflooding of intact core geometries in ASTEC V2.1: Improvements and validation on PERICLES experiments

...The injection of water into core (core reflooding) is a key Accident Management strategy to prevent or mitigate core degradation in water-cooled nuclear reactors.....

Hydraulic resistance of supercritical pressure water flowing in channels – A survey of literature

...The pressure drop in fuel assemblies is one of the main characteristics of water-cooled nuclear reactors.....

Thermal-striping analysis methodology for sodium-cooled reactor design

...These results demonstrate the applicability of engineering methods for computational thermal striping calculations, enabling thermal striping estimations in large fluid systems such as the core of a liquid metal-cooled nuclear reactor.....

Local flow structure and turbulence quantities inside a heated rectangular riser in turbulent forced and mixed convection heat transfers

...The reactor cavity cooling system (RCCS), a passive safety system in a very high temperature gas-cooled nuclear reactor (VHTR), incorporates rectangular riser channels to remove residual heat emitted from the reactor vessel, where turbulent mixed convection may occur under some emergency operation conditions.....

CFD Analysis of the VHTR Prismatic Core with Variation of Geometry Parameters

...The Very High Temperature Reactor is a thermal, graphite moderated and helium cooled nuclear reactor.....

Evaluation of local stress state due to grain-boundary sliding during creep within a crystal plasticity finite element multi-scale framework

...We pay particular consideration to effects of grain boundary sliding during creep of Type 316 stainless steel, which is used extensively in structural components of the UK fleet of Advanced Gas Cooled Nuclear Reactors (AGRs).....

Computational fluid dynamics modelling of lead natural convection and solidification in a pool type geometry

...The challenges and the lessons learned from both the experimental and numerical activities are presented to support the development of computational tools for the lead-cooled nuclear reactors and their safety assessment.....

Oxidation Behavior of an Austenitic Steel (Fe, Cr and Ni), the 310 H, in a Deaerated Supercritical Water Static System

...At supercritical temperature, water is a highly aggressive environment, and the corrosion of structural materials used in a supercritical water-cooled nuclear reactor (SCWR) is a critical problem.....

発電用原子炉

学術論文

Interfacial area concentration in gas-liquid metal two-phase flow

...The characterization and modelling of the flow features in gas and heavy liquid metal two-phase flow are required for the development of next generation nuclear reactor systems.....

Absolute radiation tolerance of amorphous alumina coatings at room temperature

...Obtained data strongly suggest that investigated material may be considered as a promising candidate for next-generation nuclear reactors, especially LFR-type, where high corrosion protection is one of the highest prerogatives to be met.....

Research on Optimization of Key Parts of Nuclear Reactor Based on Finite Element Simulation

...In view of the higher technical requirements of the third generation PWR for the control rod drive mechanism (CRDM), China's third generation nuclear reactor CRDM hook parts are designed to multi-tooth hook with wear-resistant surfacing.....

Nuclear Reactor Barge for Sustainable Energy Production

...Seaborg Technologies’ Compact Molten Salt Reactor (CMSR) is an advanced, next-generation nuclear reactor based on molten salt reactor technology which cannot melt down, explode or be used for producing nuclear weapons.....

Dislocation Loops in Proton Irradiated Uranium-Nitrogen-Oxygen System

...This work will enhance the understanding of irradiation induced microstructural evolution for uranium mononitride as an advanced nuclear fuel for the next-generation nuclear reactors.....

Comparative Studies of the Structural and Transport Properties of Molten Salt FLiNaK Using the Machine-Learned Neural Network and Reparametrized Classical Forcefields.

...This work demonstrated a computational framework that can facilitate the screening of molten salts with different chemical compositions, impurities, and additives, and at different thermodynamic conditions suitable for the next-generation nuclear reactors and thermal energy storage facilities.....

Microstructural evolution of a silicon carbide-carbon coated nanostructured ferritic alloy composite during in-situ Kr ion irradiation at 300°C 450°C

...Abstarct This work focuses on irradiation behaviors of a novel silicon carbide and carbon coated nanostructured ferritic alloy (SiC-C@NFA) composite for potential applications as a cladding and structural material for next generation nuclear reactors.....

Modeling and validation of RELAP5 for natural circulation flow in a single PWR fuel assembly

...The natural circulation loops have been widely used in the design of next generation nuclear reactors and spent fuel storage facilities.....

Review of the molten-pool sloshing motion in case of Core Disruptive Accident: Experimental and modeling studies

...Sodium-cooled Fast Reactor (SFR) is an optimized candidate of the next-generation nuclear reactor systems, while safety is a critical issue during its Research and Development (R&D) process.....

Radiation-induced mixing and demixing behavior in metallic multilayers exhibiting limited solid miscibility

...Next generation nuclear reactors demand structural materials that withstand large irradiation doses at elevated temperatures.....

Ultra-fine-grained and gradient FeCrAl alloys with outstanding work hardening capability

...FeCrAl alloy is a promising accident tolerant fuel cladding material for next generation nuclear reactors.....

System analysis methodology for decision making in the design problems of new generation nuclear reactors

...The main goal of the article is to summarize the results of many years of work on the creation of a unified methodology for designing new generation nuclear reactors that meet the requirements for generating electricity on a given scale, economic efficiency, inherent safety, and fuel supply.....

Atomistic simulations to study the effect of helium nanobubble on the shear deformation of nickel crystal

...The focus of nuclear scientists is to develop future generation nuclear reactors and predict the safe life cycle of existing nuclear structures, which are in use for a long time.....

Combined ab-initio and empirical model for irradiated metal alloys with a focus on uranium alloy fuel thermal conductivity

...The ability of our model to individually quantify the effect of different irradiation-related defects on the thermal conductivity as a function of temperature, composition, and irradiation conditions offers both a powerful tool for quantitative semi-empirical modeling of thermal conductivity in irradiated metals and materials design insight for the control of thermal conductivity in metal alloys in applications experiencing irradiation, such as next-generation nuclear reactors.....

水原子炉

学術論文

Wall-Resolved Large Eddy Simulations of the Transient Turbulent Fluid Mixing in a Closed System Replicating a Pressurized Thermal Shock

...The validation is based on experimental data held in a system reproducing various components of a pressurized water nuclear reactor, during a scenario of cold water injection at a low Atwood number of 0.....

Overview of a Theory for Planning Similar Experiments with Different Fluids at Supercritical Pressure

...The prime mover for the development of the theory was the interest in the development of Supercritical Water nuclear Reactors (SCWRs) in the frame of research being developed worldwide; however, the theory is general and can be applied to any system involving fluids at a supercritical pressure.....

Control of a pressurized light-water nuclear reactor two-point kinetics model with the performance index-oriented PSO

...The nonlinear nature of the pressurized light-water nuclear reactor (PWR) dynamics is a significant target for PSO.....

Thermal-hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

...The Economic Simplified Boiling Water Reactor (ESBWR) is a boiling water nuclear reactor of Generation III+.....

Hydrothermal corrosion of laser printed SiC fibers under extreme environment

...SiC/SiC fiber composites are proposed cladding materials to improve the accident tolerance of commercial light water nuclear reactor fuel.....

Dynamic Rod Worth Estimation with Extended Kalman Filter and Background Current Elimination

...The dynamical rod worth method (DRWM) is a fast and accurate method to measure and validate the worth of control rod during the zero power physics test at pressure water nuclear reactors.....

A Comparison of Advanced Boiling Water Reactor Simulations between Serpent/CTF and Polaris/DYN3D: Steady State Operational Characteristics and Burnup Evolution

...However, to design, develop and regulate new light water nuclear reactors there are, up until now, limited requirements for high fidelity methods due to the already well-established computational methods already being widely accepted.....

Progress in multiphase computational fluid dynamics

...This paper is primarily concerned with the development of three dimensional (3-D) multiphase computational fluid dynamics models for use in Pressurized Water Nuclear Reactor (PWR) design and analysis.....

Microstructure, Hardness, and Residual Stress of the Dissimilar Metal Weldments of SA508-309L/308L-304L

...A dissimilar metal weldment consisting of SA508-309L-308L-304L is widely used in light-water nuclear reactors.....

Improvement of Condensation Model With the Presence of Non-Condensable Gas for Thermal-Hydraulic Analysis in Containment

...Steam condensation plays a key role in prediction of the pressure behavior and hydrogen distribution in the containment during a hypothetical loss-of-coolant accident or a severe accident in a light water nuclear reactor.....

Enhanced tritium production in fusion-fission hybrids for the external consumption

...2 kg/year at a typical commercial CANDU heavy water nuclear reactor.....

IV 原子炉

学術論文

Theoretical calculation of n+235U reaction

...The design of Generation-IV nuclear reactors and the studies of advanced fuel cycles require high-precision nuclear data in the fast neutron energy region, one of the most important of which is n+235U reaction data.....

A Review of the Surface Modifications for Corrosion Mitigation of Steels in Lead and LBE

...The review paper starts with the applications of liquid metals and then concentrates on lead and lead–bismuth eutectic used in Gen IV nuclear reactors and accelerator-driven systems.....

Atom probe tomography characterization of ion and neutron irradiated Alloy 800H

...Alloy 800H is a high temperature and creep resistant alloy, and is considered as a candidate alloy for use in Generation IV nuclear reactor systems.....

Enhancement of Nanostructured Ferritic Alloy 14YWT Properties via Heat Treatment for Post-Consolidation Processing

...The nanostructured ferritic alloy 14YWT is a promising candidate for in-core use in generation IV nuclear reactors, due to a dense dispersion of insoluble, ultrafine-scale Y-Ti-O nano-oxides, which provide a high degree of irradiation tolerance and thermal stability.....

Multi-parameter fiber optic sensing for harsh nuclear environments

...The addressable harsh nuclear environment markets include Gen II, II+ and IV nuclear reactors, fusion reactors, and accelerator systems.....

Investigation of material degradation and coolant chemistry for sCO2 power cycles

...Therefore, this technology is suitable for power conversions in both high temperature non-nuclear and nuclear technologies, including the generation IV nuclear reactors [5].....

Coupled Analysis of Thorium-based Fuels in the High-Performance Light Water Reactor Fuel Assembly

...One of the six selected concepts to be part of Generation IV nuclear reactors is the Supercritical Light Water Cooled Reactor.....

Optimization of a Fuel Assembly for Supercritical Water-Cooled Reactor CSR1000

...As one of the Generation IV nuclear reactors, the SCWR (supercritical water-cooled reactor) has high economy and safety margin, good mechanical properties for its high thermal efficiency, and simplified structure design.....

On the Stability of Uranium Carbide in Aqueous Solution—Effects of HCO3– and H2O2

...Uranium carbide (UC) is a candidate fuel material for future Generation IV nuclear reactors.....

Microstructure evolution of alloy 709 during static-aging and creep-fatigue testing

...5Mo–Nb steel), a candidate structural alloy for Gen IV nuclear reactors, is expected to undergo microstructural evolution during long-term service at elevated temperatures, which in turn affects the mechanical behavior through changing contributions from precipitate and solute strengthening.....

Study on Chemical Spray Etching of Stainless Steel for Printed Circuit Heat Exchanger Channels

...As a new type of heat exchanger, printed circuit heat exchanger (PCHE) with high compactness and efficiency can be used for the supercritical carbon dioxide (SCO2) Brayton power cycle in the Gen IV nuclear reactor systems to transfer great amount of heat from nuclear reactors.....

宇宙用原子炉

学術論文

Numerical Investigation on Turbulent Flow and Heat Transfer of Helium-Xenon Gas Mixture in a Circular Tube

...Gas-cooled space nuclear reactor system usually utilizes the helium-xenon gas mixture as the working fluid.....

Research on the Fast Reset Time of Safety Rod and Implementation

...The fast reset time of the safety rod is one of the important parameters for the drive design of space nuclear reactor.....

Operation performance analysis of a liquid metal droplet radiator for space nuclear reactor

...Liquid droplet radiator (LDR) is the frameless space radiator designed for heat dissipation of large-power space nuclear reactors.....

Core power control of a space nuclear reactor based on a nonlinear model and fuzzy-PID controller

...To safely and reliably perform tasks in space with a space nuclear reactor, the control technology of the space nuclear reactor is significant.....

Energy allocation optimization of the gas-cooled space nuclear reactor

...The development of the space vehicles puts forward higher requirements on the energy supply, and the megawatt gas-cooled space nuclear reactors are promising to satisfy the demand.....

DESIGN OF A TRISO PARTICLE FUEL BASED INTEGRATED GAS-COOLED SPACE NUCLEAR REACTOR

...According to versatile and long-lasting requirements of deep space missions, space nuclear reactor (SNR) power system is becoming a more suitable choice compared to traditional solar and chemical power systems in large-scale and long-life applications.....

Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle

...Space nuclear reactor power (SNRP) using a gas-cooled reactor (GCR) and a closed Brayton cycle (CBC) is the ideal choice for future high-power space missions.....

Research on power flattening method and neutron characteristic analysis of a megawatt-class space gas-cooled fast reactor

...According to the versatility and durability requirements of the deep space missions, the space nuclear reactor (SNR) power system is becoming a more suitable choice compared with traditional solar and chemical power systems in the fields with the larger-scale and longer-life applications.....

Dynamic simulation of the gas-cooled space nuclear reactor system using SIMCODE

...One dimensional space nuclear reactor system analysis code—SIMCODE is developed and five typical transient operation conditions are calculated, including the system startup, the loss of flow accident, the loss of heat sink accident, the reactivity insertion accident, and the small loss of coolant accident.....

タイプ 原子炉

学術論文

Experimental study of SRT scrubbing model in water coolant pool

...In pool-type nuclear reactors, a postulated fuel pin failure can result in the release of fission products into the coolant pool.....

On the Delayed Hydride Cracking of the Pressure Tubes in Channel-Type Nuclear Reactors

...The data on the fracture of pressure tubes (PTs) of channel-type nuclear reactors (CANDU, Indian PHWR, and RBMK-1000) according to the delayed hydride cracking (DHC) mechanism are summarized.....

Transient Channel Sagging Measurements Under Severe Thermal Loading Condition: An Optical Imaging Approach

...As an example, in a horizontal-type nuclear reactor safety study, it is required to measure the sagging of the channels during a postulated accidental scenario analysis.....

Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding

...This paper is dedicated to an experimental program focused on the evaluation of microstructure and failure mechanisms of WWER 440 type nuclear reactor pressure vessel cladding made from Sv 08Kh19N10G2B stainless steel.....

Effect of heat treatment on microstructure and mechanical properties of boron containing Ti-Stabilized AISI-321 steel for nuclear power plant application

...Study shows that TB30 steel is more suitable material to replace the cooling water inlet and outlet tubes of VVER type nuclear reactor.....

Investigation on the hydraulic process of inertia tank in the case of pump trips

...The inertia tank (IT) used in the deep pool-type nuclear reactor (DPR) is a novel design to reduce the decrease rate of core flow in the early stage of loss of flow accident.....

Comparative Analysis of Thermal Hydraulic Parameters of AP-1000 and VVER-1200 Nuclear Reactor for Turbine Trip Concurrent with Anticipated Transient Without SCRAM (ATWS)

...Generation III+ type nuclear reactors have highly reliable active and passive safety systems with some inherent safety characteristics for attaining proper operating conditions, preventing any chance of accidents, or minimizing after-effects if any accident occurs to ensure that workers, the public and the environment are safe from undue radiation hazards.....

Failure behaviour of cladding made from Sv 07Kh25N13 austenitic stainless steel

...Due to its excellent corrosion resistance in the environment of WWER type nuclear reactor primary circuit, it is applied as anticorrosive cladding of the reactor pressure vessel.....

研究用原子炉

学術論文

Certification of a specialized source of gamma radiation spatially combined with modeling reference field of neutron radiation

...The results of metrological studies of the field of the experimental channel of the research nuclear reactor OR (experimental base of the NRC “Kurchatov Institute”) with a capacity of 0.....

The Use of Polycarbonate as Dosimeter of High Doses

...In the case of gammas, the testing was realized for 60Co and neutron radiation was studied in the light water research nuclear reactor (LVR-15).....

Structural Changes in Concrete under the Influence of Reactor Spectrum Neutrons

...The paper considers structural changes in the concrete composition that occur under the influence of neutrons of the reactor spectrum, using the example of the IR-100 research nuclear reactor, taking into account its real time and operating conditions.....

БРОМ В ЛИСТЬЯХ ТОПОЛЯ УРБАНИЗИРОВАННЫХ ТЕРРИТОРИЙ: ПРИРОДНЫЕ И АНТРОПОГЕННЫЕ ИСТОЧНИКИ ПОСТУПЛЕНИЯ

...Content of Br and other chemical elements in the ash of poplar leaves was determined by the method of instrumental neutron activation analysis in the nuclear geochemical laboratory at the educational research nuclear reactor (IRT-T) at Tomsk Polytechnic University.....

Development of FA with High-Density Fuel for Foreign Research Nuclear Reactors of Russian Design

...The results of development work on and safety validation of high-density, low-enriched fuel for research nuclear reactors of Russian design are presented.....

Engineering-Physical Makeup of the IVV-3 Research Nuclear Reactor

...A concept is presented for a pressurized, water-cooled, pool-type research nuclear reactor IVV-3 under consideration as a replacement capacity for the operating IVV-2M reactor.....

HOW TO ISOLATE RADIONUCLIDES? ON THE ELECTROCHEMICAL PURIFICATION OF TECHNOLOGICAL EQUIPMENT FROM RADIONUCLIDE CONTAMINATION — DEVELOPMENT BY CHEMISTS OF THE ACADEMY

...The method was successfully tested at the Chornobyl nuclear power plant and on the Research Nuclear Reactor of the Institute of Nuclear Research of the National Academy of Sciences of Ukraine.....

Developing of a supporting program for operator of research nuclear reactor

...The features of design and current information support of operation of research nuclear reactor IVV-2M are described.....

モジュール式原子炉

学術論文

Techno-Economic Assessment of Coal-Fired Power Unit Decarbonization Retrofit with KP-FHR Small Modular Reactors

...This analysis focuses on the repowering of a 460 MW supercritical coal-fired unit based on the Łagisza power plant design with high temperature small modular nuclear reactors based on the 320 MWth unit design by Kairos Power.....

Development of a thermal-hydraulic analysis code for thermal sizing of once-through steam generators for SMR

...A one-dimensional thermal-hydraulic analysis code was developed for the conceptual design and sizing of once-through steam generators (OTSGs) with application to small modular nuclear reactors.....

Neutronic analysis of the NuScale core using accident tolerant fuels with different coating materials

...The design flexibility of small modular nuclear reactors in synergy with accident-tolerant fuels provides a longer time to react to the loss of active cooling under severe accidents and offers comparable fuel performance during normal operation.....

Future Pathways to U.S. Decarbonization Through Nuclear and Other Energy Systems

...domestic market for factory-manufactured small modular nuclear reactors (SMRs) being developed through the use of hybrid water-energy systems.....

A strategy for achieving net-zero emissions by 2050

...Small modular nuclear reactors (SMRs) could help with background supply, but storage can be facilitated by decarbonizing the transport sector then using electric vehicles plugged into an intelligent vehicle-to-grid network also helping balance electricity flows.....

Small modular reactors (SMRs): The case of Argentina

...This chapter briefly describes activities related to small modular nuclear reactor research and development and deployment in Argentina.....

Are energy policies for supporting low-carbon power generation killing energy storage?

...The case study of energy storage systems coupled with a Small Modular nuclear Reactor (SMR) is quantitatively investigated in three scenarios: 1.....

Controllability of S-CO2 power system coupled small modular reactor with improved compressor design

...Recently, a concept of small modular nuclear reactor (SMR) coupled with an S-CO2 power cycle is proposed to target aggressively expanding SMR market.....

核融合炉

学術論文

Noble gas bubbles in bcc metals: Ab initio-based theory and kinetic Monte Carlo modeling

...Understanding the interactions of noble gases with metals is of fundamental importance for the design of radiation-resistant structural materials for fission and fusion nuclear reactors.....

Prediction of J-Integrals at Defects in W-9CR Steel Sandwich-Type Cooling Pipes

...Sandwich-type cooling pipes of the first wall of future fusion nuclear reactors (i.....

Noble Gas Bubbles in Bcc Metals: Ab Initio-Based Theory and Kinetic Monte Carlo Modeling

...Understanding the interactions of noble gases with metals is of fundamental importance for the design of radiation-resistant structural materials for fission and fusion nuclear reactors.....

Atomic-Scale Hidden Point-Defect Complexes Induce Ultrahigh-Irradiation Hardening in Tungsten.

...Tungsten displays high strength in extreme temperature and radiation environments and is considered a promising plasma facing material for fusion nuclear reactors.....

Highly stable nanocrystalline oxide dispersion strengthened alloys with outstanding helium bubble suppression

...To our best knowledge, Y50 alloy presents the best helium bubble suppression ability among all studied ODS and nanostructured ferritic alloys (NFA), which makes it a promising candidate material for using in fission and fusion nuclear reactors.....

Characterization of the nature and morphology of coarse precipitation in various oxide dispersion strengthened steels

...Oxide Dispersion Strengthened (ODS) steels are candidate materials for both fission and fusion nuclear reactors.....

Study of a stainless steel porous membrane for recovering tritium from Pb-Li alloys: Assessment of mass transfer coefficient

...The eutectic Pb-Li alloy is used as liquid breeding blanket material in the concept design of future fusion nuclear reactors where the effective extraction of generated tritium is an important unit operation of the fusion fuel cycle.....

塩原子炉

学術論文

Reactor with Circulating Fuel Based on Molten Metal Fluorides for Np, Am, Cm Incineration

...Variants of Np, Am, Cm incineration using a portion of the plutonium from VVER-1000, -1200 spent fuel in a high-power molten-salt nuclear reactor (MSR) with a cavity-type core and fuel salts with the compositions Li,Be,An/F and Li,Na,K,An/F are discussed.....

4D-STEM Imaging of nanostructural heterogeneities in Ni-20Cr after corrosion in molten salt

...In molten salt nuclear reactors, the structural materials in contact with the high temperature (above 600 ̊C) salt could also develop such heterogeneities.....

Effect of Li metal addition on corrosion control of Hastelloy N and stainless steel 316H in molten LiF-NaF-KF

...Molten fluoride salts are used in various energy harvesting applications such as solar collectors and molten salt nuclear reactors (MSRs).....

Recent developments for molten salt systems in Thermochimica

...The modified quasi-chemical model in the quadruplet approximation has been implemented in the open-source equilibrium thermodynamics library Thermochimica, enabling single point equilibrium calculations and sophisticated multi-physics simulations of molten salt nuclear reactor systems.....

Complex Structure of Molten NaCl–CrCl3 Salt: Cr–Cl Octahedral Network and Intermediate-Range Order

...The resurgence of the molten-salt nuclear reactors (MSRs) creates interesting problems in molten-salt chemistry.....

Validating modern methods for impurity analysis in fluoride salts

...Salt impurities directly affect degradation of structural materials in molten salt environments, so impurity quantification and analysis of salts is important for the deployment of next generation molten salt nuclear reactors.....

革新的な原子炉

学術論文

Simulating the Production of Medical Radioisotopes in a Fast Thorium-Cycle ADS with SERPENT

...Beside this, innovative nuclear reactors are advocated as solutions to the issues of nuclear waste production and proliferation threats.....

The concept of inherent safety of generation V nuclear power plants

...The authors also discuss the conditions for the generation and development of new self-protection means for innovative nuclear reactors as well as the phenomenological and technical aspects for their implementation based on the deterministic formalism.....

Great achievements of M. Salvatores for nuclear data adjustment study with use of integral experiments

...In the design of innovative nuclear reactors such as fast reactors, the improvement of the prediction accuracies for neutronics properties is an important task.....

Improved 242Pu(n,$ \gamma$γ) thermal cross section combining activation and prompt gamma analysis

...A good knowledge of the radiative capture cross section of 242Pu is required for innovative nuclear reactor studies, especially for MoX fuel reactors.....

別の原子炉

学術論文

Feasibility study of application of ThO2 fuel rods in VVER-1000 fuel assemblies using MCNP and ORIGEN codes

...‎Many types of thorium-based fuels were applied in different nuclear reactors‎.....

Preliminary Core Design of the Solid Moderator Reactor for Investigation of the In-Depth Europa Ice Layer

...The use of different nuclear reactor systems as power source of deep-space explorers has been studied over the past decades as solar power cannot be expected in deep-space beyond Jupiter.....

Cost Analysis of Nuclear Hydrogen Production Using IAEA-HEEP 4 Software

...These hydrogen production technologies can be coupled with different nuclear reactors based on the heat required in the process.....

Advances in nuclear hydrogen production: Results from an IAEA international collaborative research project

...The paper also presents the results of country-specific case studies considering different nuclear reactors and hydrogen technologies.....

チェルノブイリ原子炉

学術論文

Activity of 137Cs and 40K Isotopes in Pine (Pinus sylvestris L.) and Birch (Betula pendula Roth) Stands of Different Ages in a Selected Area of Eastern Poland

...(4) Conclusions: the results show a much greater radioactive contamination of the environment in eastern Poland during the testing with nuclear weapons than after the Chernobyl nuclear reactor explosion.....

Investigating the microstructure and mechanical behaviour of simulant “lava-like” fuel containing materials from the Chernobyl reactor unit 4 meltdown

...Decommissioning of the damaged Chernobyl nuclear reactor Unit 4 is a top priority for the global community.....

Plutopia. Nuclear Families, Atomic Cities, and the Great Soviet and American Plutonium Disasters, by Kate Brown. Oxford: Oxford University Press; 2013.

...PLUTOPIA HAS been on my reading list for a while, but it moved to the top because of the controversy surrounding the author’s recent book, Manual for Survival, over the health effects consequent to the Chernobyl nuclear reactor accident in northern Ukraine in 1986.....

Investigating the Microstructure and Mechanical Behavior of Simulant ‘Lava-Like’ Fuel Containing Materials From the Chernobyl Reactor Unit 4 Meltdown

...Decommissioning of the damaged Chernobyl nuclear reactor Unit 4 is a top priority for the global community.....

自然の原子炉

学術論文

Limited expression of the Paleoproterozoic Oklo natural nuclear reactor phenomenon in the aftermath of a widespread deoxygenation event ~2.11–2.06 billion years ago

...These data suggest that, although ultramafic to mafic igneous rocks of the Mesoarchean Belinga Group, and to some extent Archean granitoids, were likely important sources of V to the Francevillian U deposits, they were not the only source of the abnormally high V concentrations in the U deposits that did not produce natural nuclear reactors.....

The Oklo spontaneous nuclear reactor case: a fireball startup creating the South Atlantic

...There is a need to clarify continental formation processes and the Oklo natural nuclear reactor happens to be in the exact position where such a natural phenomena needs to be to explain continental separation.....

Long-term retention and chemical fractionation of fissionogenic Cs and Tc in Oklo natural nuclear reactor fuel

...We present the results of a coordinated NAUTILUS and NanoSIMS isotopic study of epsilon (e) phase metallic aggregates from the Oklo natural nuclear reactor zone (RZ) 13.....

小型原子炉

学術論文

Reliability and redundancy allocation analysis applied to a nuclear protection system

...Brazil is constructing with national technology two small nuclear reactors for propulsion and for radioisotope production with thermal power levels between 20 and 50 MW.....

Study on Reactor Core Physics Calculation of Marine Nuclear Power Platform

...The marine nuclear power platform is an organic combination of small nuclear reactor and ship engineering technology.....

Design and economic analysis of a novel hybrid nuclear-solar complementary power system for power generation and desalination

...A small nuclear reactor and a solar tower receiver are integrated in this multi-energy complementary system.....

既存の原子炉

学術論文

Nanoindentation Test of F321 Austenitic Stainless Steel Under Fe-ion Irradiation

...Understanding such degradation is important for predicting the evolution of material behavior under irradiation and extending the lifespan of existing nuclear reactors.....

FUEL-CYCLE SCENARIO TO REDUCE RADIOACTIVE WASTE FROM LIGHT-WATER REACTOR

...One of the promising solutions is to transmute the TRU nuclides to those with lesser radioactivity and radiotoxicity in the existing nuclear reactors.....

Design and analysis of nuclear and solar-based energy, food, fuel, and water production system for an indigenous community

...As a case study, the Saugeen First Nation indigenous community in the Bruce Peninsula in Ontario, Canada, is selected for meeting the demands of useful commodities where an integration of a newly developed multigenerational system with an existing nuclear reactor is achieved in order to provide food security, supply the freshwater for drinking purposes, and meet the community's electricity and heat demands.....

大型原子炉

学術論文

Can small modular reactors help mitigate climate change?

...Lower power outputs of these reactors will likely result in higher costs in comparison to large nuclear reactors, and even if they achieve parity, will fail economically, since large reactors are themselves struggling to compete with renewable sources of electricity.....

Monte Carlo Simulation Study of Hot-Particle Detection in Voluminous Samples by Gamma Spectrometry

...In this work, we addressed the inhomogeneity problem in gamma spectrometry caused by hot particles, which are dispersed into environment from large nuclear reactor accidents such as at Chernobyl and Fukushima.....

Transport, constructability, and economic advantages of SMR modularization

...Existing work on large nuclear reactor modularization is used to generate a module breakdown scheme for both small and large reactors and a module reconfiguration strategy is proposed that allows modules to fit within road transportable weight and dimension limits.....

ベッド原子炉

学術論文

Experimental investigation of turbulent characteristics in pore-scale regions of porous media

...The study of flow dynamics in porous media or randomly packed beds is essential because these systems are commonly applied in a wide array of engineering applications, such as thermal energy storage, catalytic reactors for processing and distillation, oil recovery, fuel cells, and pebble bed nuclear reactor cores.....

Heat transfer and fluid flow of helium coolant in a model of the core zone of a pebble-bed nuclear reactor

...Using the RNG k-e model of turbulence in the approximation for porous media, a numerical study of fluid flow and heat transfer in a model of the core zone of a pebble-bed nuclear reactor was performed.....

Development of an HTR-Type nuclear and bifacial PV solar based integrated system to meet the needs of energy, food and fuel for sustainable indigenous cities

...The high-temperature reactor (HTR)-type pebble bed nuclear reactors are considered to be used with the copper chlorine Cu-Cl hydrogen production cycle, bifacial photovoltaic (PV) plant, gas and steam turbines, greenhouse, fish farm and residential heating systems, and multi-effect water desalination in the integrated multigenerational system.....

原子炉の関与

学術論文

Moving particle semi-implicit simulation on the molten Wood’s metal downward relocation process

...In the case of a severe accident involving nuclear reactors, an important aspect that should be considered is the leakage of molten material from the inside of the reactor into the environment.....

SIMULATOR ASSISTED ENGINEERING – APPLICATIONS IN NUCLEAR ENGINEERING EDUCATION AT KHALIFA UNIVERSITY

...The Generic Pressurized Water Reactor (GPWR) simulator has been used in the Nuclear I&C Laboratory at Khalifa University (KU) since 2013 to improve student performance in nuclear engineering that is a multidisciplinary field involving nuclear reactor physics, thermodynamics, fluid mechanics, thermal hydraulics, radiation, etc.....

Gamma ray shielding capabilities of rhenium-based superalloys

...ABSTRACT Because of the high radiation dose in applications involving nuclear reactors, medical treatments etc.....

Pwr原子炉

学術論文

Fuel rod nonlinear vibrations to detect and characterize Pellet-Cladding Interaction

...Pellet-Cladding Interaction (PCI) in a Light Water Reactor is one of the major concerns to guarantee clad integrity while attempting at increasing the flexibility of PWR nuclear reactor operations to follow power grid demand.....

Novel solution to the fractional neutron point kinetic equation using conformable derivatives

...The methodology developed is applied to cases with one and six groups of delayed neutrons in abrupt reactivity changes in the reactor, and for the dynamics of startup of PWR nuclear reactor.....

減速型原子炉

学術論文

Computational fluid dynamics assessment of the Helium-3 Enhanced Negative Reactivity Insertion (HENRI) system for the Transient REActor Test (TREAT) facility

...The Transient REActor Test facility (TREAT) is an air-cooled, graphite moderated nuclear reactor that is used for irradiation testing of nuclear fuels and materials.....

Mimicking irradiation-induced cracking of nuclear graphite using bromine intercalation

...Keyway root cracking and radiolytic weight loss in graphite moderated nuclear reactors may limit future successful operation of the civil nuclear fleet.....

亜臨界原子炉

学術論文

High power particle accelerator for driving the nuclear waste transmutation system at nuclear power plant

...ATW is subcritical nuclear reactor combined with high power proton accelerator for transmutation of nuclear waste utilizing neutrons from spallation reaction due to collision of high power proton beam with heavy metal material as spallation target.....

A fully adaptive nonintrusive reduced-order modelling approach for parametrized time-dependent problems

...The second was a lid-driven cavity test, and the last was a neutron diffusion problem in a subcritical nuclear reactor with 11 parameters.....

未来の原子炉

学術論文

Application of Positron Annihilation Spectroscopy in Accelerator-Based Irradiation Experiments

...These experiments use hydrogen, helium, heavy ions, and their combination to simulate various radiation environments of future nuclear reactors or nuclear research facilities.....

Ultrahigh hardness in Y2O3 dispersed ferrous multicomponent nanocomposites

...Oxide dispersion strengthened Fe-based steels are one of the candidate materials for applications in future nuclear reactors, an operation that needs superior mechanical properties and long-term microstructural stability at elevated temperatures.....

原子炉の運転

学術論文

Lesson Learned on Handling Volcanic Ash of Kartini Reactor

...This paper will discuss how to deal with the impact of volcanic ash on Kartini reactor and lesson learned for other operating nuclear reactors around the world.....

Distributed Fiber Sensors With High Spatial Resolution in Extreme Radiation Environments in Nuclear Reactor Cores

...To the best of our knowledge, we present for the first time, the temperature profile of an operating nuclear reactor core with 3-cm spatial resolution, enabled by distributed fiber sensors with laser-enhanced Rayleigh scattering profiles.....

模型原子炉

学術論文

MATLAB PDE toolbox for 2-D and 3-D neutron diffusion simulations

...This research extends MATLAB PDE Toolbox to model nuclear reactors by solving the 2-D and 3-D multigroup neutron diffusion equations using the finite element method.....

Numerical analysis of the neutron multigroup SP N equations

...The multigroup neutron SPN equations, which are an approximation of the neutron transport equation, are used to model nuclear reactor cores.....

高速原子炉

学術論文

In situ Monitoring of the Oxidation of Coated and Uncoated Austenitic Stainless Steels at Temperatures Lower than 600 °C: Part A—Coating Screening

...The lithium niobate used in an ultrasonic transducer for liquid metal fast nuclear reactors is prone to a reduction leading to a rapid short circuit of the sensor in operating conditions.....

Fuel cycle considerations for uranium, plutonium and minor actinide partitioning and transmutation

...In this regard, a summary is provided of the results from two international studies led by Max Salvatores in which the authors participated: (1) the expert group on Homogeneous versus Heterogeneous Recycling of Transuranics in Fast Nuclear Reactors, and (2) the expert group on Potential Benefits and Impacts of Advanced Nuclear Fuel Cycles with Actinide Partitioning and Transmutation.....

スケール原子炉

学術論文

Analysis of nuclear-renewable hybrid energy system for marine ships

...Small scale nuclear reactors, such as Small Modular Reactors (SMRs) and Microreactors (MRs), are free from GHG emissions and are competitive candidates to replace fossil fuel-based generators.....

Optimal Planning of Integrated Nuclear-Renewable Energy System for Marine Ships Using Artificial Intelligence Algorithm

...Nuclear energy is emissions-free energy, and small-scale nuclear reactors like Microreactors (MRs) are competent to replace fossil fuel-based generators.....

原子炉全体

学術論文

A hybrid porous model for full reactor core scale CFD investigation of a prismatic HTGR

...Three-dimensional (3-D) Computational Fluid Dynamics (CFD) analysis of a whole nuclear reactor core is a great challenge due to the large geometric volume and complex structures.....

Research on non-uniform control rod for PWR

...The uneven distribution of the axial power even endangers the safety and economy of the whole nuclear reactor.....

照射された原子炉

学術論文

Monte Carlo neutronics benchmarks on nuclear fuel depletion: A review

...These simulations can estimate the inventory of isotopes in neutron irradiated nuclear reactor fuel.....

Suppression of Helium Induced Cracking in Laser Repair Welding of Highly Irradiated Stainless Steels

...Welding repair of irradiated nuclear reactor materials such as austenitic stainless steels used for the reactor internals has been challenging due to irradiation generated helium in the material matrix over an extended period of time.....

Core Nuclear Reactor

学術論文

TOWARDS CAD-BASED GEOMETRY MODELLING WITH THE RANDOM RAY METHOD

...The Advanced Random Ray Code (ARRC) is a high performance computing application capable of high-fidelity simulations of full core nuclear reactor models.....

Fatigue crack growth behaviour in proton irradiated austenitic stainless steel

...Many in-core nuclear reactor components that are subjected to radiation damage and repeated thermal stresses are made from austenitic stainless steels.....

1000 原子炉

学術論文

Re-evaluation of level 2 PSA results of a VVER-1000 NPP with consideration of innovative severe accident management strategies

...The objective is to reduce the contribution of severe accidents to the large and early release frequencies of radioactive materials for a VVER-1000 nuclear reactor.....

Predicting behavior of AP-1000 nuclear reactor fuel rod under steady state operating condition by using FRAPCON-4.0 software

...This paper reports the results on the predictions of behavior of AP-1000 nuclear reactorfuel rod under steady state operating condition by using FRAPCON-4.....

新しい原子炉

学術論文

Nuclear data target accuracy requirements for advanced reactors: The ALFRED case

...Uncertainties estimation is essential for a sound assessment and a clear definition of safety margins, which in turn are crucial for licensing approval of new nuclear reactors by safety authorities.....

核分裂原子炉

学術論文

Deviating from the pure MAX phase concept: Radiation-tolerant nanostructured dual-phase Cr2AlC

...The irradiation resistance of the material was assessed using a 300-keV Xe ion beam in situ within a transmission electron microscope up to 40 displacements per atom at 623 K: a condition that extrapolates the harmful environments of future fusion and fission nuclear reactors.....

Anthropogenic tritium: Inventory, discharge, environmental behavior and health effects

...This characteristic gradually becomes more and more prominent along with the rapid development of fusion energy research in particular and operations of fission nuclear reactors as well.....

安全な原子炉

学術論文

Application of Atom Probe Tomography as a Method to Investigate Localized Thermal Transport in Actinide-Bearing Oxides

...There is an imperative need to understand this as long-term safe nuclear reactor operation is contingent on nuclear fuel efficiency, which is directly affected by localized thermal transport in these materials.....

Calculation and Analysis of Critical Heat Flux at LWR Passive Safety Design

...Critical heat flux (MDNBR) is one parameter for safe nuclear reactor operation.....

Breeder Nuclear Reactor

学術論文

A study on sodium - the fast breeder reactor coolant

...The application of this element in liquid form at high temperature as a coolant in fast breeder nuclear reactors necessitated development of sodium technology.....

Fluid-structure interaction of a 7-rods bundle: Benchmarking numerical simulations with experimental data

...Fluid flows through rod bundles are observed in many nuclear applications, such as in the core of Gen IV liquid metal fast breeder nuclear reactors (LMFBR).....

原子炉コア

学術論文

CFD simulation on the transient process of coolant mixing phenomenon in reactor pressure vessel

...The emergency coolant cooling system (ECCS) is designed to inject coolant into reactor pressure vessel (RPV) during loss of coolant accidents, ensuring the sufficient coolant inventory in the nuclear reactor core.....

Thermal-hydraulic two-phase modeling of reactivity-initiated transients with CATHARE2 – Application to SPERT-IV simulation

...Reactivity-Initiated Accidents (RIA) in nuclear reactor cores are very complex multiphysic transients.....

Experimental investigation of turbulent characteristics in pore-scale regions of porous media

...The study of flow dynamics in porous media or randomly packed beds is essential because these systems are commonly applied in a wide array of engineering applications, such as thermal energy storage, catalytic reactors for processing and distillation, oil recovery, fuel cells, and pebble bed nuclear reactor cores.....

LES and URANS study on turbulent flow through 3 × 3 rod bundle with spacer grid and mixing vanes using spectral element method

...In this paper, the turbulent flow in rod bundles with spacer grid and mixing vanes in nuclear reactor core was studied using spectral element method with large eddy simulation (LES) and unsteady RANS (URANS) method.....

Prediction method for thermal-hydraulic parameters of nuclear reactor system based on deep learning algorithm

...The nuclear reactor core and the steam generator are the core components of nuclear reactor system, which directly determine the heat releasing and carrying capacity of nuclear reactor system.....

Study and Conceptual Design on Cryogenic-Nuclear Propulsion System for Interplanetary & Leo Mission

...This design of combined propulsion system will focus more on CPS, to be used as a source of propellant for achieving higher specific impulse and thrust while in the atmosphere and in outer space with NTS and to provide more efficient cooling for Nuclear reactor core and the Nozzle.....

Evaluating the Diffusion Approximation Capability on the Integral Pressurized Water Reactor (IPWR) Core Calculation

...Diffusion approximation is an important approximation used to model a nuclear reactor core with a quite good accuracy and less computational cost.....

UNCERTAINTY CHARACTERIZATION FRAMEWORK FOR STEADY-STATE AND TRANSIENT NEUTRONICS SIMULATIONS OF A CANDU REACTOR

...This paper reports on the development and testing of a comprehensive few-group cross section input uncertainty library for the NESTLE-C nodal diffusion-based nuclear reactor core simulator.....

Monitoring System for an Experimental Facility Using GMDH Methodology

...The nuclear reactor core is represented by an electrical heater with different values of power.....

Research on the automatic generation code for nuclear fuel reloading patterns in pressurized water-cooled reactors

...A 3D nuclear reactor core neutronic code, COCO, is used for the calculation of F ΔH value and reactor cycle length.....

Numerical analysis of the neutron multigroup SP N equations

...The multigroup neutron SPN equations, which are an approximation of the neutron transport equation, are used to model nuclear reactor cores.....

Axial power distribution control in fast nuclear reactor based on proportional spatial-derivative method

...However, the nuclear reactor core has a typical distributed parameters feature.....

Core Power Modelling of High-Temperature Engineering Test Reactor (HTTR) Using Nonlinear Least Squares Method for Parameter Estimation

...In this paper, a nonlinear mathematical model of the nuclear reactor core was derived in derivative form using fundamental principles.....

A hybrid porous model for full reactor core scale CFD investigation of a prismatic HTGR

...Three-dimensional (3-D) Computational Fluid Dynamics (CFD) analysis of a whole nuclear reactor core is a great challenge due to the large geometric volume and complex structures.....

NUMA-AWARE DATA MANAGEMENT FOR NEUTRON CROSS SECTION DATA IN CONTINUOUS ENERGY MONTE CARLO NEUTRON TRANSPORT SIMULATION

...MC simulations of full nuclear reactor cores are computationally expensive, making high-accuracy simulations impractical for most routine reactor analysis tasks because of their long time to solution.....

Regeneration of Fiber Bragg Gratings and Their Responses Under X-Rays

...It withstands temperatures as high as 1000 °C, opening the way to new application fields such as the temperature monitoring of the nuclear reactor cores.....

Feasibility of full-core pin resolved CFD simulations of small modular reactor with momentum sources

...Complex flow structure interactions and heat transfer processes take place in nuclear reactor cores.....

Study on the subcooled boiling pressure drop for downward flow in a narrow rectangular channel

...Subcooled boiling pressure drop is an issue worthy of attention for heat exchange systems, such as nuclear reactor core.....

Optimal and fast field reconstruction with reduced basis and limited observations: Application to reactor core online monitoring

...The result is helpful for the practical implementation of the neutronic field reconstruction methods with reduced basis and limited observations in nuclear reactor cores.....

AI-based design of a nuclear reactor core

...The authors developed an artificial intelligence (AI)-based algorithm for the design and optimization of a nuclear reactor core based on a flexible geometry and demonstrated a 3× improvement in the selected performance metric: temperature peaking factor.....

Development of a multi-physics coupling system based on ICoCo interface and its validation on NEA-OECD core transient benchmark

...The prediction capabilities of CORCA-K/CORTH are proved by the analysis of the NEA-OECD rod ejection transient benchmark, which proves that the developed coupling system CORCA-K/CORTH has good accuracy in nuclear reactor core transient calculation.....

Upscaled heat transfer coefficients for a liquid metal-cooled fast nuclear reactor

...We upscaled the local energy equation of a fuel pin and its surrounding liquid metal (cooler fluid) to the whole fuel assembly representing the entire nuclear reactor core.....

ADAPTIVE SOLUTION OF THE NEUTRON DIFFUSION EQUATION WITH HETEROGENEOUS COEFFICIENTS USING THE MIXED FINITE ELEMENT METHOD ON STRUCTURED MESHES

...The neutron transport equation can be used to model the physics of the nuclear reactor core.....

Small break loss of coolant accident of 200 cm² in cold leg of primary loop of Angra2 nuclear power reactor evaluation

...The results obtained for ANGRA 2 nuclear reactor core during the postulated accident were satisfactory when compared with the FSAR-A2.....

Thermal hydraulic analysis of a PWR loaded with annular fuel rods

...The thermal hydraulic conditions were calculated with the aid of the VIPRE subchannel code, which is a widely used tool in the analysis of nuclear reactor cores.....

Distributed Fiber Sensors With High Spatial Resolution in Extreme Radiation Environments in Nuclear Reactor Cores

...To the best of our knowledge, we present for the first time, the temperature profile of an operating nuclear reactor core with 3-cm spatial resolution, enabled by distributed fiber sensors with laser-enhanced Rayleigh scattering profiles.....

Modelling study of the potential release of contaminated water from storage tanks at the Fukushima Dai-ichi NPP into marine environment

...To prevent the further release of highly contaminated water, which was used for cooling the overheated nuclear reactor cores, and groundwater, which was continuously pumped out the reactor buildings, a large number of tanks was installed in the area around NPP to collect all this water.....

Application of the collective model to determine some rotational bands of 239U nucleus

...U material is component in fuels of nuclear reactor core.....

原子炉システム

学術論文

Interfacial area concentration in gas-liquid metal two-phase flow

...The characterization and modelling of the flow features in gas and heavy liquid metal two-phase flow are required for the development of next generation nuclear reactor systems.....

Comparative studies of iterative methods for solving the “optimally diffusive” coarse mesh finite difference accelerated transport equation

...The emergence of advanced nuclear reactor systems with increasing complexity and heterogeneity has necessitated detailed high fidelity neutronic analysis.....

Atom probe tomography characterization of ion and neutron irradiated Alloy 800H

...Alloy 800H is a high temperature and creep resistant alloy, and is considered as a candidate alloy for use in Generation IV nuclear reactor systems.....

Numerical Investigation on Turbulent Flow and Heat Transfer of Helium-Xenon Gas Mixture in a Circular Tube

...Gas-cooled space nuclear reactor system usually utilizes the helium-xenon gas mixture as the working fluid.....

IDENTIFICATION OF REACTOR PHYSICS BENCHMARKS FOR NUCLEAR DATA TESTING: TOOLS AND EXAMPLES

...Measurements of reactor physics quantities aimed at identifying the reactivity worth of materials, spectral ratios of cross-sections, and reactivity coefficients have ensured reactor physics codes can accurately predict nuclear reactor systems.....

Data-Driven-Based Forecasting of Two-Phase Flow Parameters in Rectangular Channel

...In the current nuclear reactor system analysis codes, the interfacial area concentration and void fraction are mainly obtained through empirical relations based on different flow regime maps.....

Correction to: Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges

...The article “Thermal hydraulic considerations of nuclear reactor systems: Past, present and future challenges” written by Guan Heng Yeoh, was originally published electronically on the publisher’s internet portal (currently SpringerLink) on 08 April 2019 without open access.....

Carbon-Based Nanofluids and Their Advances towards Heat Transfer Applications—A Review

...Furthermore, it assesses the influence of these advanced working fluids on parabolic trough solar collectors, nuclear reactor systems, and air conditioning and refrigeration systems.....

Validation of SAS4A/SASSYS-1 for predicting steady-state single-phase natural circulation

...The validation of system analysis codes for nuclear reactor systems is required for the development and application of these computational tools.....

Preliminary Core Design of the Solid Moderator Reactor for Investigation of the In-Depth Europa Ice Layer

...The use of different nuclear reactor systems as power source of deep-space explorers has been studied over the past decades as solar power cannot be expected in deep-space beyond Jupiter.....

Statistical Mechanics-Based Surrogates for Scalar Transport in Channel Flow

...Thermal hydraulics, in certain components of nuclear reactor systems, involve complex flow scenarios, such as flows assisted by free jets and stratified flows leading to turbulent mixing and thermal fluctuations.....

Redundant Actuators without Direct Communication for Reactor Control Rod Positioning

...In the design of nuclear reactor systems, reliability is always a top consideration.....

New direction of nuclear code development: artificial intelligence

...In this chapter, we provide a brief summary of the history of AI and the previous efforts on introducing AI to nuclear reactor systems in 1980s.....

Recent developments for molten salt systems in Thermochimica

...The modified quasi-chemical model in the quadruplet approximation has been implemented in the open-source equilibrium thermodynamics library Thermochimica, enabling single point equilibrium calculations and sophisticated multi-physics simulations of molten salt nuclear reactor systems.....

Review of the molten-pool sloshing motion in case of Core Disruptive Accident: Experimental and modeling studies

...Sodium-cooled Fast Reactor (SFR) is an optimized candidate of the next-generation nuclear reactor systems, while safety is a critical issue during its Research and Development (R&D) process.....

Machine Learning-Based Methodology for Assessment of Doppler Reactivity of Sodium-Cooled Fast Reactor

...In order to close nuclear fuel cycle and address the problem of sustainability, advanced nuclear reactor systems of the fourth generation are in the focus of the research for many years.....

Scaling analysis of the hydraulic behavior in reactor pressure vessel

...The hydraulic behavior of coolant flow in reactor pressure vessel plays an important role in the thermal hydraulic and safety analysis of nuclear reactor system.....

RE-EVALUATION OF THE TSL FOR YTTRIUM HYDRIDE

...Yttrium hydride (YHx) is of interest as a high-temperature moderator material in advanced nuclear reactor systems because of its superior ability to retain hydrogen at elevated temperatures.....

Dynamic simulation of the gas-cooled space nuclear reactor system using SIMCODE

...One dimensional space nuclear reactor system analysis code—SIMCODE is developed and five typical transient operation conditions are calculated, including the system startup, the loss of flow accident, the loss of heat sink accident, the reactivity insertion accident, and the small loss of coolant accident.....

Study on Chemical Spray Etching of Stainless Steel for Printed Circuit Heat Exchanger Channels

...As a new type of heat exchanger, printed circuit heat exchanger (PCHE) with high compactness and efficiency can be used for the supercritical carbon dioxide (SCO2) Brayton power cycle in the Gen IV nuclear reactor systems to transfer great amount of heat from nuclear reactors.....

Numerical investigation on local heat transfer characteristics of S-CO2 in horizontal semicircular microtube

...The nuclear reactor system with supercritical carbon dioxide (S-CO2) as working fluid has good prospects in generation IV reactors.....

原子炉設計

学術論文

Trace xenon detection in helium environment via laser-induced breakdown spectroscopy

...There is significant motivation to develop and deploy novel nuclear reactor designs to deliver improved performance, safety, and economics for nuclear energy.....

Fate and transport of unruptured tri-structural isotropic (TRISO) fuel particles in the event of environmental release for advanced and micro reactor applications.

...Advanced nuclear reactor designs and advanced fuel types offer safety features that may reduce environmental consequences in an accident scenario when compared to conventional reactors and fuels.....

Method of Characteristics for 3D, Full-Core Neutron Transport on Unstructured Mesh

...A myriad of nuclear reactor designs are currently being considered for next-generation power production.....

Liquid spray modeling under sodium fire accidents

...The Sodium-Cooled Fast Reactor (SFR) system, which features a fast-spectrum, sodium-cooled reactor and a closed fuel cycle for efficient management of actinides and conversion of fertile uranium, is rather prominent in the nuclear reactor design in Generation IV (Gen IV), and likely to be widespreadly used and well-constructed all over the world.....

Temperature-Dependent Properties of Molten Li2BeF4 Salt Using Ab Initio Molecular Dynamics

...Molten lithium tetrafluoroberyllate (Li2BeF4) salt, also known as FLiBe, with a 2:1 mixture of LiF and BeF2 is being proposed as a coolant and solvent in advanced nuclear reactor designs, such as the molten salt reactor or the fluoride salt cooled high-temperature reactor.....

High-throughput ion irradiation of additively manufactured compositionally complex alloys

...Several advanced nuclear reactor designs promise efficiency and safety improvements over the current reactor fleet but are limited by the current set of ASME code-qualified materials.....

Analysis of printed circuit heat exchanger (PCHE) for Small modular molten salt reactor (MSR)

...The Heat exchanger is played a crucial role in the nuclear reactor design where the size compaction and efficiency improvement two issues that must be solved.....

Challenges and concerns for development of nuclear thermal-hydraulics

...In the area of applications to nuclear reactor design and safety an emblem for this situation is exhibited by system computer codes: their new development began a quarter of a century ago and current predictive capabilities are not better than those available before.....

A statistical model of irradiation hardening induced by non-periodic irradiation defects

...Numerous efforts have been made to develop the irradiation hardening models, due to their important role in nuclear reactor design and service lifetime prediction.....

CTF and FLOCAL Thermal Hydraulics Validations and Verifications within a Multiscale and Multiphysics Software Development

...Simulation codes allow one to reduce the high conservativism in nuclear reactor design improving the reliability and sustainability associated with nuclear power.....

What can nuclear engineers learn from design research? A review of the theory and evidence from contemporary American and French nuclear reactor design projects

...Although nuclear reactor design is recognized as an essential skill and intellectual output of academic nuclear engineering, little attention has been paid within the discipline to the structure of the reactor design process and factors influencing design outcomes.....

Indirect validation of fluid-to-fluid scaling criteria for modeling steam condensation based on empirical correlations and CFD simulations

...Several nuclear reactor designs have adopted passive safety systems with condensation inside horizontal tubes, such as the Passive Auxiliary Feedwater System (PAFS) of the APR+, the new generation of the Korean-Standard Pressurized Water Reactors (PWR).....

Depletion chain optimization of lattice code STREAM for LWR fuel assembly burnup analysis

...The simplified burnup chain is tested on the 16 LWR fuel assembly depletion problems from the Virtual Environment for Reactor Application (VERA) benchmarks, including burnable poison (BP) pin cells commonly used in nuclear reactor design such as gadolinia, Pyrex, AIC, B4C and IFBA, and one OPR-1000 fuel assembly with gadolinium bearing fuel depletion problem.....

原子炉物理学

学術論文

“CHAPTER 5” DIFFUSION THEORY

...In many nuclear reactor physics texts (excluding Elmer Lewis’s recent text however), “Chapter 5” is dedicated to diffusion theory; hence, the title of this submission.....

Virtual element methods for the spatial discretisation of the multigroup neutron diffusion equation on polygonal meshes with applications to nuclear reactor physics

...This paper presents the first application of VEM to the field of nuclear reactor physics, specifically to the steady-state, multigroup, neutron diffusion equation (NDE).....

On some features of the eigenvalue problem for the PN approximation of the neutron transport equation

...The standard multiplication eigenvalue that is particularly relevant for nuclear reactor physics applications is analysed, together with the time eigenvalue, including also the contribution of delayed neutrons.....

Multiobjective Core Reloading Pattern Optimization of PARR-1 Using Modified Genetic Algorithm Coupled with Monte Carlo Methods

...For an optimal reactor core reloading design strategy, an intelligent technique GA is coupled with the Monte Carlo (MC) code SuperMC developed by the FDS team in China for nuclear reactor physics calculations.....

Spatial adaptivity of the SAAF and Weighted Least Squares (WLS) forms of the neutron transport equation using constraint based, locally refined, isogeometric analysis (IGA) with dual weighted residual (DWR) error measures

...The nuclear reactor physics verification benchmark test cases show that both AMR algorithms are superior to uniform refinement with respect to accuracy per degree of freedom.....

Analysis of the neutron noise induced by fuel assembly vibrations

...The investigation of neutron noise is key to several applications in nuclear reactor physics, such as the detection of control rod or assembly vibrations and the diagnostic of coolant speed and void fraction.....

Neutrons probability distribution of the coupled reactors kinetics system via Magnus expansion

...The precise modeling of nuclear reactor physics is an essential topic of research that advances improve strategies, methods, and models.....

Fractal neutrons diffusion equation: Uniformization of heat and fuel burn-up in nuclear reactor

...These terms are major in nuclear reactor physics since the magnitude of energy dissipation in fission depends on the position and nature of interaction.....

Making sense of uncertain nuclear data

...Massimo Salvatores has made significant contributions to the fields of nuclear reactor physics, nuclear data, and uncertainty quantification and propagation.....

SIMULATOR ASSISTED ENGINEERING – APPLICATIONS IN NUCLEAR ENGINEERING EDUCATION AT KHALIFA UNIVERSITY

...The Generic Pressurized Water Reactor (GPWR) simulator has been used in the Nuclear I&C Laboratory at Khalifa University (KU) since 2013 to improve student performance in nuclear engineering that is a multidisciplinary field involving nuclear reactor physics, thermodynamics, fluid mechanics, thermal hydraulics, radiation, etc.....

Exact weight cancellation in Monte Carlo eigenvalue transport problems.

...In this paper we examine such a case from the field of nuclear reactor physics, where the negative particle weights prevent the power iteration algorithm from converging on the sought fundamental eigenstate of the Boltzmann transport equation.....

A new approach for nuclear reactor analysis based on complex network theory

...In this work, complex network theory is applied for the first time in the field of nuclear reactor physics to present a new approach for the evaluation of the multiplication factor of a nuclear system.....

原子炉の安全

学術論文

MD Simulation of Hundred-Billion-Metal-Atom Cascade Collision on Sunway Taihulight

...Radiation damage to the steel material of reactor pressure vessels is a major threat to the nuclear reactor safety.....

Commissioning of an MRI test facility for CFD-grade flow experiments in replicas of nuclear fuel assemblies and other reactor components

...A new test facility is presented, enabling single-phase isothermal fluid mechanics experiments to support nuclear reactor safety studies.....

Transient Channel Sagging Measurements Under Severe Thermal Loading Condition: An Optical Imaging Approach

...As an example, in a horizontal-type nuclear reactor safety study, it is required to measure the sagging of the channels during a postulated accidental scenario analysis.....

Experimental investigation on minimum film boiling temperature during reflooding in multi-rectangular narrow channels

...Determination of minimum film boiling temperature (Tmin) is significant in the nuclear reactor safety analysis.....

Development and coupling of the 1-D neutronics code PoKiMON with ANSYS CFX for reactor shutdown simulations

...Nowadays, nuclear reactor safety simulations of real nuclear plants are still performed using approximated system codes which rely on one-dimensional lumped-parameters or subchannel methods.....

An old issue and a new challenge for nuclear reactor safety

...Nuclear reactor safety (NRS) and the branch accident analysis (AA) constitute proven technologies: these are based on, among the other things, long lasting research and operational experience in the area of water cooled nuclear reactors (WCNR).....

A hyperbolic phase-transition model coupled to tabulated EoS for two-phase flows in fast depressurizations

...The final model is implemented in the EUROPLEXUS code for its use in nuclear reactor safety.....

CFD study on onset of liquid entrainment through ADS-4 branch line in AP1000

...Therefore, the accurate knowledge of the Onset of Liquid Entrainment (OLE) is critical to nuclear reactor safety (NRS) assessment.....

Nuclear Power Plants Are Not So Safe: Fluid Transients / Water Hammers, Autoignition, Explosions, Accident Predictions and Ethics

...Previous publications inaccurately, unethically, and inappropriately assessed reactor safety with respect to other industries and natural disasters, where nuclear industry publications non-conservatively applied data to promote nuclear reactor safety, and published models skewed accident data to present nuclear energy as safer than it is.....

Thermal hydraulic analysis of core flow bypass in a typical research reactor

...The main objective of nuclear reactor safety is to maintain the nuclear fuel in a thermally safe condition with enough safety margins during normal operation and anticipated operational occurrences.....

原子炉事故

学術論文

Knowledge on radiation emergency preparedness among nuclear medicine technologists

...031) and more willing to assist with radiation detection or monitoring in the event of nuclear reactor accident (P = 0.....

Interaction of cesium bound fission product compounds (CsI and CsOH) with abundant inorganic compounds of atmosphere: Effect on hygroscopic growth properties.

...Hence neglecting the presence of atmospheric salts affects the accuracy of the source term estimates for a postulated nuclear reactor accident scenario.....

A mobile simulation and ARIMA modeling for prediction of air radiation dose rates

...The findings of this study demonstrate that an appropriate ARIMA model can be applied for radiation dose time-series in the case of nuclear reactor accidents like Chernobyl and Fukushima to predict the future air dose rates, which can provide valuable information in determining the evacuation zones, decontamination processes, and radiation protection progresses.....

External Dose to Recovery Teams Following a Wide-area Nuclear or Radiological Release Event

...The common radionuclide 137Cs is a gamma-ray source term for nuclear reactor accidents, nuclear detonations, and potential radionuclide dispersal devices.....

Isotopic Inventory and Activity Calculations of Fukushima Daiichi Unit-1 Accident

...Several published studies dealt with the calculation of core inventory and source term for nuclear reactor accidents using different methodologies and assumptions or through the measurements of the environmental samples around the reactor site.....

Plutopia. Nuclear Families, Atomic Cities, and the Great Soviet and American Plutonium Disasters, by Kate Brown. Oxford: Oxford University Press; 2013.

...PLUTOPIA HAS been on my reading list for a while, but it moved to the top because of the controversy surrounding the author’s recent book, Manual for Survival, over the health effects consequent to the Chernobyl nuclear reactor accident in northern Ukraine in 1986.....

A mobile simulation and ARIMA modeling for prediction of air radiation dose rates

...The findings of this study demonstrate that an appropriate ARIMA model can be applied for radiation dose time-series in the case of nuclear reactor accidents like Chernobyl and Fukushima to predict the future air dose rates, which can provide valuable information in determining the evacuation zones, decontamination processes, and radiation protection progresses.....

Influence of non-equilibrium sorption on the vertical migration of 137Cs in forest mineral soils of Fukushima prefecture

...Sorption hypotheses and models are required for the prediction of 137Cs migration in soils contaminated after nuclear reactor accidents and nuclear weapons tests.....

Monte Carlo Simulation Study of Hot-Particle Detection in Voluminous Samples by Gamma Spectrometry

...In this work, we addressed the inhomogeneity problem in gamma spectrometry caused by hot particles, which are dispersed into environment from large nuclear reactor accidents such as at Chernobyl and Fukushima.....

Influence of non-equilibrium sorption on the vertical migration of 137Cs in forest mineral soils of Fukushima Prefecture.

...Sorption hypotheses and models are required for the prediction of 137Cs migration in soils contaminated after nuclear reactor accidents and nuclear weapons tests.....

原子炉コンポーネント

学術論文

Mechanical behavior of additively manufactured and wrought 316L stainless steels before and after neutron irradiation

...Fabrication of nuclear reactor components using additive manufacturing (AM) methods is now a practical option since the AM technologies have advanced to allow for building of complex parts with high quality materials.....

Microstructural and High Temperature Wear Characteristics of Plasma Transferred Arc Hardfaced Ni–Cr–Si–B-C Alloy Deposits

...Due to the tough working environments, wear damage to nuclear reactor components is frequent.....

Safely probing the chemistry of Chernobyl nuclear fuel using micro-focus X-ray analysis

...A fascinating mixture of molten UO2, nuclear fuel cladding, concrete, stainless steel and other nuclear reactor components, these materials behaved like lava, solidifying to form a complex, highly radioactive glass-ceramic.....

Emergence of micro-galvanic corrosion in plastically deformed austenitic stainless steels

...Localized plastic deformation has been observed to render nuclear reactor components more susceptible to stress corrosion cracking (SCC).....

DYN3D and CTF Coupling within a Multiscale and Multiphysics Software Development (Part I)

...Understanding and optimizing the relation between nuclear reactor components or physical phenomena allows us to improve the economics and safety of nuclear reactors, deliver new nuclear reactor designs, and educate nuclear staff.....

Temperature adjusted cross section libraries used for criticality calculations

...The change in the temperature of the nuclear reactor components (fuel, moderator, coolant, and structural materials) is considered to be a significant source of reactivity variation.....

Fatigue crack growth behaviour in proton irradiated austenitic stainless steel

...Many in-core nuclear reactor components that are subjected to radiation damage and repeated thermal stresses are made from austenitic stainless steels.....

Advanced sensor for in situ, NDE monitoring of nuclear reactors components integrity

...Proposed advanced laser sensor and technology which allow to detect corrosion, mechanical stress and defects which can prevent nuclear fuel failure caused by mechanical and physical-chemical aspects of nuclear reactor components under high level nuclear radiation.....

原子炉格納容器

学術論文

Towards Uncertainty Quantification of LES and URANS for the Buoyancy-Driven Mixing Process between Two Miscible Fluids—Differentially Heated Cavity of Aspect Ratio 4

...In the field of Computational Fluid Dynamics (CFD), the reliable prediction of hydrogen distribution and pressure build-up in nuclear reactor containment after a severe reactor accident is a representative application where the assessment of these uncertainties is of essential importance.....

CFD simulations of stratified layer erosion in MiniPanda facility using the tailored CFD solver containmentFOAM

...Turbulent gas mixing in a buoyant flow with density gradient is an important physical mechanism in many applications ranging from industrial gaseous emissions into the atmosphere to nuclear reactor containment flows.....

Taming next‐generation HPC systems: Run‐time system and algorithmic advancements

...These advancements are crucial for successfully parallelizing such complex applications as simulating geophysical flows, solving ordinary differential equations (ODEs), structural analysis of nuclear reactor containment buildings, solving generalized eigenvalue problems, modeling of material science phenomena, and others.....

Integral effect test for steam line break with coupling reactor coolant system and containment using ATLAS-CUBE facility

...To improve safety analysis technology for a nuclear reactor containment considering an interaction between a reactor coolant system (RCS) and containment, this study aims at an experimental investigation on the integrated simulation of the RCS and containment, with an integral effect test facility, ATLAS-CUBE.....

Behavior of cementitious SSC’s in mitigating accidents

...Three cases were selected to be included in this chapter that represent different accidental conditions in three facilities, namely, radioactive waste disposal, dry spent fuel storage, and nuclear reactor containment.....

Implementation of a CFD model for wall condensation in the presence of non-condensable gas mixtures

...In this paper, we discuss a CFD model to predict vapor condensation on walls in the presence of non-condensable gases, with a specific focus on large scale applications, such as accidental flows in a nuclear reactor containment.....

Large eddy fire simulation applications from nuclear industry

...There are several applications in nuclear industry like room fires, wildland fires, smoke or ash disposal, hydrogen transport in nuclear reactor containment, natural convection in building flows etc.....

Analysis on the blast resistance of steel concrete composite slab

...The new type composite slab has been widely used in nuclear reactor containment, offshore platform and oil storage tank.....

原子炉運転

学術論文

Fuel rod nonlinear vibrations to detect and characterize Pellet-Cladding Interaction

...Pellet-Cladding Interaction (PCI) in a Light Water Reactor is one of the major concerns to guarantee clad integrity while attempting at increasing the flexibility of PWR nuclear reactor operations to follow power grid demand.....

Sensitivity analysis of BISON model for characterization of impact of experimental parameters on hydrogen migration and redistribution in zirconium-based alloys

...The formation of hydrides, a result from excess hydrogen picked up by the cladding during nuclear reactor operation, can significantly impact cladding integrity.....

Thermal behaviour of caesium implanted in UO2: A comparative study with the xenon behaviour

...Annealing under reducing atmosphere (Ar/H2 5 %) was performed at 1000 °C or 1600 °C, which corresponds respectively to a representative temperature during nuclear reactor operation (at the centre of the fuel pellets) and during an accident.....

Design of a compact detector for nuclear-fuel-rod enrichment detection

...Nuclear fuel rods are an important component of nuclear reactor operation.....

Study Protocol for radiation exposure and cancer risk assessment- The Taiwan Nuclear Power Plants and Epidemiology Cohort Study (TNPECS).

...BACKGROUND This cohort was established to evaluate whether 38-year radiation exposure (since the start of nuclear reactor operations) is related to cancer risk in residents near three near nuclear power plants (NPPs).....

Application of Atom Probe Tomography as a Method to Investigate Localized Thermal Transport in Actinide-Bearing Oxides

...There is an imperative need to understand this as long-term safe nuclear reactor operation is contingent on nuclear fuel efficiency, which is directly affected by localized thermal transport in these materials.....

Calculation and Analysis of Critical Heat Flux at LWR Passive Safety Design

...Critical heat flux (MDNBR) is one parameter for safe nuclear reactor operation.....

原子炉燃料

学術論文

Numerical investigation of the effect of mixing vanes on subcooled boiling in a 3 × 3 rod bundle channel with spacer grid

...Mixing vane grids (MVGs) are an integral part of nuclear reactor fuel assembly, and significantly impact the flow and heat transfer characteristics of the coolant in a rod bundle channel.....

Dynamic Characteristics Analysis of Cylinders Bundle Coupling System Under Axial Flow

...Nuclear reactor fuel assemblies are mainly composed of cylinders bundle(CB), calculating the dynamics characteristics of CB under axial flow can lay a foundation for predicting fretting wear and vibration fatigue.....

Challenges and Opportunities to Alloyed and Composite Fuel Architectures to Mitigate High Uranium Density Fuel Oxidation: Uranium Silicide

...Several high uranium density fuels are under consideration for deployment as accident tolerant and/or advanced technology nuclear reactor fuels, including UN, U3Si2, UC and UB2.....

Hydrothermal corrosion of laser printed SiC fibers under extreme environment

...SiC/SiC fiber composites are proposed cladding materials to improve the accident tolerance of commercial light water nuclear reactor fuel.....

Monte Carlo neutronics benchmarks on nuclear fuel depletion: A review

...These simulations can estimate the inventory of isotopes in neutron irradiated nuclear reactor fuel.....

Modeling and neutronic analysis of pin-cell comprising nuclear fuel with different chemical composition and neutron moderator using Monte Carlo code OpenMC

...Selection of a perfect nuclear reactor fuel demands the neutronic analysis of the available fuel materials in particular reactor environment.....

Instability of U3Si2 in pressurized water media at elevated temperatures

...Following the Fukushima Daiichi accident, significant efforts from industry and the scientific community have been directed towards the development of alternative nuclear reactor fuels with enhanced accident tolerance.....

原子炉のコンセプト

学術論文

Direct numerical simulation of fluid flow in a 5x5 square rod bundle

...Characterization of parallel flow through rod bundles is of key importance in assessing the performance and safety of several engineering systems, including a majority of nuclear reactor concepts.....

Predicting structural material degradation in advanced nuclear reactors with ion irradiation

...Swelling associated with the formation and growth of cavities is among the most damaging of radiation-induced degradation modes for structural materials in advanced nuclear reactor concepts.....

Metallic Fast Reactor Separate Effect Studies for Fuel Safety

...Sodium-cooled Fast Reactors (SFR) are one of the advanced nuclear reactor concepts to be commercially applied for electricity production.....

An integrated experimental and computational investigation of defect and microstructural effects on thermal transport in thorium dioxide

...Advanced nuclear reactor concepts aim to use fuels that must withstand unprecedented temperature and radiation extremes.....

THERMAL SCATTERING LAW ENDF LIBRARIES FOR LIQUID FLIBE

...Several advanced nuclear reactor concepts have been proposed in the past few years where FLiBe molten salt represents a major constituent of the core.....

原子炉冷却

学術論文

Numerical prediction of high temperature thermal contact resistance of HTA–C/ZrB2-SiC with radiation effects

...High temperature thermal contact resistance is the research focus of many applications involving thermo-mechanical issues including spacecraft thermal protection, nuclear reactor cooling and heat treatment process.....

Geometry aspect review of the natural circulation system as innovation in passive cooling of nuclear reactor

...The passive nuclear reactor cooling system has become a fascinating topic, especially since the nuclear incident in Fukushima Daiichi, Japan.....

Finite element analysis of unsteady MHD Blasius and Sakiadis flow with radiation and thermal convection using Cattaneo-Christov heat flux model

...Many technical processes involving hydromagnetics flows and thermal expansion in the porous medium have been studied in recent years, such as casting, compact heat exchangers, liquid metal filtering, fusion control, and nuclear reactor cooling.....

SVM and Naïve Bayes Models for Estimation of Key Process Variables in Nuclear Power Plant

...In this paper, we introduce classification models using data mining methods to improve the performance of a typical nuclear reactor cooling pump lubrication system process.....

Investigation of heat transfer characteristics using Fe3O4 nanofluid along with TT inserts in tube with uniform electromagnetic field

...It can be used in various applications of heat exchangers like automobile radiator cooling, data centre cooling, nuclear reactor cooling, etc.....

原子炉技術

学術論文

Forced Convection Heat Transfer of Zirconia-water Nanofluid in Vertical Triangular Sub-channel

...Recent studies showed that ZrO2-water nanofluid has a good prospect to be used in the nuclear reactor technology due to its low neutron absorption cross section.....

Review of interdisciplinary heat transfer enhancement technology for nuclear reactor

...All over the world, the nuclear reactor technology has been in the critical stage of transformation and upgrading.....

RDE Design Strategy for Indonesia Experimental NPP

...The main goal of initiating the RDE design Program, beside developing the national capability as a nuclear reactor technology provider by mastering the design, construction project management, commissioning and operation of a nuclear power reactor, is to mastering nuclear power plant that to be able to be scaled-up and commercialized to support the national energy security.....

Safety Analysis of Small Modular Natural Circulation Lead-Cooled Fast Reactor SNCLFR-100 Under Unprotected Transient

...SNCLFR-100 is a small modular natural circulation lead-cooled fast reactor, developed by University of Science and Technology of China, aiming at taking full advantage of the good economics and inherent safety of lead-cooled fast reactors to develop miniaturized, lightweight and multi-purpose special nuclear reactor technology.....

原子炉の電力

学術論文

Experimental research on double-hole steam condensation effects and models under different diameters and pitch to diameter ratios conditions

...The multi-hole steam Direct Contact Condensation (DCC) is of high efficiency in mass and heat transfer, which has been widely used in the engineering application, especially the advanced nuclear reactor power plant passive safety system.....

A differentiator based second-order sliding-mode control of a pressurized water nuclear research reactor considering Xenon concentration feedback

...This paper presents the Twisting control algorithm with a differentiator to extend the applicability of the second-order sliding-mode control scheme in a nuclear reactor power control and regulation.....

A solar thermal storage power generation system based on lunar in-situ resources utilization: modeling and analysis

...The evaluated launch mass of designed power system has a competitive advantage than those of nuclear reactor power and photovoltaic-battery power systems.....

Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle

...Space nuclear reactor power (SNRP) using a gas-cooled reactor (GCR) and a closed Brayton cycle (CBC) is the ideal choice for future high-power space missions.....

原子炉建屋

学術論文

Influence of Vertical Equivalent Damping Ratio on Seismic Isolation Effectiveness of Nuclear Reactor Building

...A comparative study of the seismic response in terms of acceleration floor response spectra (FRS), peak acceleration, displacement response of the nuclear reactor building, and dynamic response of the 3D-CIB was carried out.....

Study of isolation effectiveness of nuclear reactor building with three-dimensional seismic base isolation

...Hence, four different combinations of CDSB were designed for the 3D-CIB and employed to isolate nuclear reactor building.....

Radon Concentrations in a Nuclear Reactor Center in Brazil

...The objective of this study was to evaluate the 222Rn concentrations in the radiochemistry and radiometric laboratories in the nuclear reactor building of the Nuclear Reactor Center (CERPq) located in the Institute of Nuclear and Energy Research (IPEN), São Paulo, Brazil.....

Numerical models in geotechnics including soil-structure interaction

...This chapter highlights how SSI can be applied to massive foundations, including nuclear reactor buildings.....

原子炉圧力

学術論文

Microstructure and Failure Processes of Reactor Pressure Vessel Austenitic Cladding

...This paper is dedicated to an experimental program focused on the evaluation of microstructure and failure mechanisms of WWER 440 type nuclear reactor pressure vessel cladding made from Sv 08Kh19N10G2B stainless steel.....

Gamma-ray irradiation effects on CdTe solar cell dosimeter

...Compact and radiation-tolerant radiation dosimeter without bias voltage application using solar cells such as CdTe was proposed for severe radiation environment near a nuclear reactor pressure vessel.....

Effect of Neutron Irradiation on the Mechanical Properties of an A508 CL2 and 15Kh2NMFA Irradiated in the NOMAD_3 Rig in the BR2 Cooling Water

...The typical operating temperatures of a nuclear reactor pressure vessel in a PWR are between 290°C and 300°C.....

Radiation problems of functional testing of nuclear power plant equipment at an electrophysical installation of the INR of NAS of Ukraine

...The method and program of measures developed to measure the intensity of radiation fields in the premises of the INR of NAS of Ukraine experimental installation and in adjacent territories in the generation modes of intense electron fluxes, bremsstrahlung gamma radiation and mixed gamma electron radiation fields similar to the conditions of nuclear reactor pressure zones are discussed.....

原子炉モデル

学術論文

An Experimental Study into the Hydrodynamics of the Loop Coolant Flows’ Mixing in the Nuclear Reactor Downcomer

...In the article, an experimental testbench and a nuclear reactor model under investigation are described, the measurement methods are set forth, and the operating variables at which the study was conducted and the obtained results are provided.....

TOWARDS CAD-BASED GEOMETRY MODELLING WITH THE RANDOM RAY METHOD

...The Advanced Random Ray Code (ARRC) is a high performance computing application capable of high-fidelity simulations of full core nuclear reactor models.....

Validation of Covert Cognizance Active Defenses

...A nuclear reactor model is employed for demonstration.....

Load-following control of nuclear reactors based on fuzzy input-output model

...Corresponding to a specified equilibrium power family, the nonlinear nuclear reactor model is described as the Linear Parameter-Varying (LPV) form.....

原子炉エリア

学術論文

Synthesis, physical properties, and gamma–ray shielding capacity of different Ni-based super alloys

...The prepared alloys can be considered useful candidates in radiation shielding applications to reduce workers' exposure in the nuclear reactor area and medical centers.....

Gamma-ray shielding capacity of different B4C-, Re-, and Ni-based superalloys

...The prepared alloys can be considered useful candidates in radiation shielding applications to reduce workers' exposure in the nuclear reactor area and medical centers.....

Microstructure and mechanical properties of a functionally graded material from TA1 to Inconel 625 fabricated by dual wire + arc additive manufacturing

...Functionally graded material (FGM) from Ti to Ni alloy has potential applications in extreme environment condition such as aerospace or nuclear reactor area.....

原子炉熱

学術論文

CFD/RELAP5 coupling analysis of the ISP No. 43 boron dilution experiment

...Multi-dimensional coupling analysis is a research hot spot in nuclear reactor thermal hydraulic study and both the full-scale system transient response and local key three-dimensional thermal hydraulic phenomenon could be obtained simultaneously, which can achieve the balance between efficiency and accuracy in the numerical simulation of nuclear reactor.....

40th Anniversary of the first international topical meeting on nuclear reactor thermal-hydraulics: Highlights of thermal-hydraulics research in the past four decades

...The year 2020 marks the 40th anniversary of the first International Topical Meeting on Nuclear Reactor Thermal-hydraulics (NURETH-1).....

Progress in reflood thermal hydraulics studies in the past 40 years

...Accurate simulation of reflood transients of a reactor core is one of the top priorities for nuclear reactor thermal–hydraulic and safety analysis.....

原子炉の爆発

学術論文

Activity of 137Cs and 40K Isotopes in Pine (Pinus sylvestris L.) and Birch (Betula pendula Roth) Stands of Different Ages in a Selected Area of Eastern Poland

...(4) Conclusions: the results show a much greater radioactive contamination of the environment in eastern Poland during the testing with nuclear weapons than after the Chernobyl nuclear reactor explosion.....

Prologue: The Refugee Experience

...More people than ever before in history are living as refugees The first part of their article presents a general account of the experiences of refugees during the last five years during which Italy was rocked by political turbulence and the COVID-19 crisis Following their review of some of the psychoanalytic literature on the refugee experience, they report on a study they conducted with refugees of the Fukushima earthquake, tsunami and nuclear reactor explosion [Extracted from the article] Copyright of Psychoanalytic Inquiry is the property of Taylor & Francis Ltd and its content may not be copied or emailed to multiple sites or posted to a listserv without the copyright holder's express written permission However, users may print, download, or email articles for individual use This abstract may be abridged No warranty is given about the accuracy of the copy Users should refer to the original published version of the material for the full abstract (Copyright applies to all s ).....

Are We All Refugees?

...Then with reference to a study of the refugees of the Fukushima earthquake, tsunami and nuclear reactor explosions, it discusses the societal traumas that drive people out of their homes.....

原子炉への応用

学術論文

Helium effects and bubbles formation in irradiated Ti3SiC2

...Ti3SiC2 is a potential structural material for nuclear reactor applications.....

Effect of Irradiation on Ni-Inconel/Incoloy Heterostructures in Multimetallic Layered Composites

...We use molecular dynamics (MD) to study radiation-induced mixing through multi-metallic layered composites' interfaces for nuclear reactor applications.....

Nano-amorphous layers improve the helium swelling resistance of a CAC-type nanocomposite

...This result sheds light on the design of radiation-tolerant materials for advanced nuclear reactor applications.....

原子炉冷却材

学術論文

Positioning Accuracy Determination of the Servo Axes for Grinding Wavy-Tilt-Dam Seals Using a Four-Axis Grinder

...The wavy-tilt-dam (WTD) seal is considered to be one of the ideal sealing patterns used in nuclear reactor coolant pumps (RCPs).....

Adaptive predictive control of average coolant temperature based on chaotic particle swarm optimization

...Aiming at the problem that the average temperature control system of nuclear reactor coolant under variable conditions is nonlinear and time-varying, and the traditional fixed model cannot meet the control requirements, an improved generalized predictive control method with adaptive identification of model parameters is proposed.....

Radiative heat transfer of nanomaterial on a convectively heated circular tube with activation energy and nanoparticle aggregation kinematic effects

...The scope of nanomaterials can be seen in various engineering and industrial fields such as nuclear reactor coolants, heat exchangers, aircraft coolants, microreactor coolants, automobile radiators, solar collectors, etc.....

原子炉制御

学術論文

3He proportional counter development for thermal neutron detection

...This last characteristic has ensured that this detector is one of the best tools for thermal neutron flux measurements in a nuclear reactor control.....

Human factors engineering and participatory design in the project of a nuclear research reactor control centre

...The HFE program main purpose is to ensure that human factor practices are incorporated into the plant design, emphasizing man-machine interface issues and design improvement of the nuclear reactor Control Centre.....

原子炉計算

学術論文

A Robust, Relaxation–Free Multiphysics Iteration Scheme for CMFD–Accelerated Neutron Transport k–Eigenvalue Calculations–I: Theory

...This paper presents a new robust scheme for coupled physics nuclear reactor calculations.....

HIGH-FIDELITY EX-CORE CAPABILITIES IN VERA

...High-fidelity nuclear reactor calculations have become increasingly important when considering lifetime extensions of the current nuclear fleet.....

原子炉ユニット

学術論文

Investigating the microstructure and mechanical behaviour of simulant “lava-like” fuel containing materials from the Chernobyl reactor unit 4 meltdown

...Decommissioning of the damaged Chernobyl nuclear reactor Unit 4 is a top priority for the global community.....

Investigating the Microstructure and Mechanical Behavior of Simulant ‘Lava-Like’ Fuel Containing Materials From the Chernobyl Reactor Unit 4 Meltdown

...Decommissioning of the damaged Chernobyl nuclear reactor Unit 4 is a top priority for the global community.....

原子炉シミュレーション

学術論文

ONIX: An open-source depletion code

...It is an open-source depletion software to be used for nuclear reactor simulations, for fissile material production analysis as well as for nuclear arms control applications.....

Methodology for Sensitivity Analysis of Homogenized Cross-Sections to Instantaneous and Historical Lattice Conditions with Application to AP1000® PWR Lattice

...In the two-step method for nuclear reactor simulation, lattice physics calculations are performed to compute homogenized cross-sections for a variety of burnups and lattice configurations.....

原子炉環境

学術論文

Long-term initiation time for stress -corrosion cracking of alloy 600 with implications in stainless steel: Review and analysis for nuclear application

...This paper provides a summary and analysis on the initiation of stress -corrosion cracking (SCC) of Alloy 600 (and related alloys) and stainless steels in nuclear reactor environments near 300 °C.....

In-situ 4D-STEM imaging to develop a fundamental understanding of coupled transport of vacancies

...Extreme nuclear reactor environments require materials to maintain their integrity all while a range of processes act in unison to degrade their performance.....

原子炉材料

学術論文

Suppression of Helium Induced Cracking in Laser Repair Welding of Highly Irradiated Stainless Steels

...Welding repair of irradiated nuclear reactor materials such as austenitic stainless steels used for the reactor internals has been challenging due to irradiation generated helium in the material matrix over an extended period of time.....

Post-Irradiation Analysis of Additively Manufactured Stainless Steel 316L Specimens

...Nuclear reactor materials are known to be susceptible to hardening and embrittlement, irradiation-assisted stress corrosion cracking, and void swelling when exposed to high temperature radiation fields for long periods of time (Was and Andresen, 2012).....

Nuclear Reactor Ivv

学術論文

Engineering-Physical Makeup of the IVV-3 Research Nuclear Reactor

...A concept is presented for a pressurized, water-cooled, pool-type research nuclear reactor IVV-3 under consideration as a replacement capacity for the operating IVV-2M reactor.....

Developing of a supporting program for operator of research nuclear reactor

...The features of design and current information support of operation of research nuclear reactor IVV-2M are described.....

科学ニュース

辞書

定義と意味

Nuclear

形容詞

  • (兵器 原子の、原子核に関する、または原子核を構成する 細胞の、細胞の核に関する、または細胞の核を構成する 核を構成する、または核のようなもの
  • Reactor

    名詞

  • 回路にリアクタンスを導入するために使用される電気装置 (物理
  • クイズ