Advanced Nuclear(첨단 핵)란 무엇입니까?
Advanced Nuclear 첨단 핵 - Changes to system costs and investments from including carbon removal are larger as policy ambition increases, reducing the dependence on technologies like advanced nuclear and long-duration storage. [1] We provide a detailed calculation of the relative costs of the following technologies: new pulverized coal, new pulverized coal with CCS, natural gas combined cycle, natural gas with CCS, biomass-fueled plant, biomass with CCS, advanced nuclear, wind (for small and medium penetration levels), solar, wind with backup (for large penetration levels), co-firing of coal and biomass combined with CCS, and advanced CCS on natural gas. [2]탄소 제거를 포함하여 시스템 비용 및 투자에 대한 변화는 정책 목표가 증가함에 따라 더 커지고 첨단 원자력 및 장기 저장과 같은 기술에 대한 의존도를 줄입니다. [1] 우리는 다음 기술의 상대 비용에 대한 자세한 계산을 제공합니다. 신 미분탄, CCS가 있는 신 미분탄, 천연 가스 복합 순환, CCS가 있는 천연 가스, 바이오매스 연료 플랜트, CCS가 있는 바이오매스, 첨단 원자력, 풍력(소규모 및 중간 침투 수준), 태양열, 백업이 포함된 풍력(대규모 침투 수준의 경우), CCS와 결합된 석탄 및 바이오매스의 동시 연소, 천연 가스에 대한 고급 CCS. [2]
passive safety system 수동적 안전 시스템
Various passive safety systems have been developed for advanced nuclear reactors. [1] In advanced nuclear power plant such as the AP1000 passive safety system, pool boiling is also used to fulfil the residual heat removal function through the Passive Residual Heat Removal Heat Exchanger (PRHR HX). [2] 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. [3] The Passive Residual Heat Removal Heat Exchanger (PRHR HX) is an important equipment of the passive safety system in advanced nuclear power plants such as AP1000. [4] The framework is applied to the case study of a generic Passive Safety System (PSS) for Decay Heat Removal (DHR) designed for advanced Nuclear Power Plants (NPPs). [5] Passive Safety Systems (PSSs) are increasingly employed in advanced Nuclear Power Plants (NPPs). [6] Passive safety systems are currently implemented or under consideration in several advanced nuclear plants. [7] 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. [8] 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. [9]첨단 원자로를 위한 다양한 수동적 안전 시스템이 개발되었습니다. [1] AP1000 수동안전시스템과 같은 첨단 원자력발전소에서는 PRHR HX(Passive Residual Residual Removal Heat Exchanger)를 통한 잔류열 제거 기능을 수행하기 위해 Pool Boiling도 사용됩니다. [2] nan [3] nan [4] nan [5] nan [6] 수동적 안전 시스템은 현재 여러 첨단 원자력 발전소에서 구현되거나 고려 중입니다. [7] nan [8] nan [9]
Several Advanced Nuclear 여러 첨단 핵
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. [1] Passive safety systems are currently implemented or under consideration in several advanced nuclear plants. [2] Several advanced nuclear reactor concepts have been proposed in the past few years where FLiBe molten salt represents a major constituent of the core. [3] Several advanced nuclear reactors use Tristructural-isotropic (TRISO) fuel particles randomly distributed in a matrix to allow for aggressive operating conditions. [4]몇몇 고급 원자로 설계는 현재 원자로에 비해 효율성과 안전성 향상을 약속하지만 현재 ASME 코드 적격 재료 세트에 의해 제한됩니다. [1] 수동적 안전 시스템은 현재 여러 첨단 원자력 발전소에서 구현되거나 고려 중입니다. [2] nan [3] nan [4]
Driven Advanced Nuclear
The Compact Materials Irradiation Facility (CMIF) project will provide a high-energy, high-flux neutron source for material irradiation research which will be indispensable for the long-term Accelerator-Driven Advanced Nuclear Energy (ADANE) project in China. [1] A project of Accelerator Driven Advanced Nuclear Energy System (ADANES) has been proposed in China. [2] ADS is a key part of the accelerator-driven advanced nuclear energy system (ADANES), and its research and development (R&D) will play a very important role in promoting China’s energy transformation and stimulating the innovative development of China’s nuclear energy industry. [3]CMIF(Compact Materials Irradiation Facility) 프로젝트는 중국의 장기 가속기 구동 첨단 원자력(ADANE) 프로젝트에 필수 불가결한 물질 조사 연구를 위한 고에너지, 고유속 중성자 소스를 제공할 것입니다. [1] 가속기 구동 첨단 원자력 시스템(ADANES) 프로젝트가 중국에서 제안되었습니다. [2] nan [3]
Future Advanced Nuclear
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. [1] To provide a basic understanding of the synergy effect of hydrogen and helium on structural materials for future advanced nuclear systems, the vacancy-type defects in SIMP steel induced by separate and sequential H and He implantation at room temperature was investigated using positron annihilation Doppler broadening spectroscopy (DBS) and transmission electron microscopy (TEM). [2]고선량 조사에 노출되는 원자로용 공학적 재료는 다양한 방사선 손상을 일으켜 재료의 성능 저하를 초래하여 미래의 첨단 원자로에 재료의 적용을 심각하게 제한합니다. [1] 미래 첨단 원자력 시스템의 구조 재료에 대한 수소와 헬륨의 시너지 효과에 대한 기본 이해를 제공하기 위해 상온에서 분리되고 순차적인 H 및 He 주입에 의해 유도된 SIMP 강철의 공공형 결함을 양전자 소멸 도플러 확장 분광법을 사용하여 조사했습니다. (DBS) 및 투과 전자 현미경(TEM). [2]
Designing Advanced Nuclear
The Monte Carlo photon transport code IMPC-Photon is developed for serving the software development of designing advanced nuclear energy system such as Accelerator Driven Advanced Nuclear Energy System (ADANES) in Chinese Academy of Sciences. [1] However, fundamental understanding of such complex micro- and meso-structures on radionuclide diffusion and uptake kinetics is lacking, which is essential for designing advanced nuclear wasteform materials. [2]Monte Carlo 광자 전송 코드 IMPC-Photon은 중국과학원의 ADANES(가속기 구동 첨단 원자력 시스템)와 같은 첨단 원자력 시스템 설계 소프트웨어 개발을 위해 개발되었습니다. [1] 그러나 방사성핵종 확산 및 흡수 동역학에 대한 이러한 복잡한 마이크로 및 메조 구조에 대한 기본적인 이해가 부족하며, 이는 고급 핵폐기물 형태 재료를 설계하는 데 필수적입니다. [2]
Developing Advanced Nuclear
The world's nuclear energy community is exploring and developing advanced nuclear energy technology with a view to solving the economic, safety and environmental issues in the development of nuclear energy. [1] Understanding the irradiation hardening effect of structural steels under various irradiation conditions plays an important role in developing advanced nuclear systems. [2]advanced nuclear reactor 첨단 원자로
Our task was to develop an extension of the Multi-Objective Optimization by Ratio Analysis (MULTIMOORA) for advanced nuclear reactor prioritization in developing countries. [1] 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. [2] The emergence of advanced nuclear reactor systems with increasing complexity and heterogeneity has necessitated detailed high fidelity neutronic analysis. [3] Various passive safety systems have been developed for advanced nuclear reactors. [4] In simulation of advanced nuclear reactors, requirements like high precision, high efficiency and convenient to multi-physics coupling are putting forward. [5] 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. [6] 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. [7] 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. [8] 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. [9] These alloys are of interest for structural applications in advanced nuclear reactors. [10] 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. [11] Moreover, related research data to the study of the effect of fluid flow rate on one of the advanced nuclear reactors, namely the Molten Salt Reactor and the effect of loop geometry experimentally, are presented in this study for enrichment purposes. [12] 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. [13] Sodium-cooled Fast Reactors (SFR) are one of the advanced nuclear reactor concepts to be commercially applied for electricity production. [14] Designed as a comprehensive system analysis code for advanced nuclear reactors, SAS4A/SASSYS-1 requires validation of its physics model for capturing single-phase natural circulation behavior. [15] 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. [16] The desire for reducing our carbon footprint is driving significant interest in advanced nuclear reactors to produce energy. [17] Method The study was conducted in a full-scope control room research simulator of an advanced nuclear reactor. [18] Graphene-reinforced nickel matrix nanocomposites with high-density interfaces are recommended as candidate materials for advanced nuclear reactors because of the potential irradiation tolerance. [19] The attractive mechanical properties and superior resistance to void-swelling make ferritic/martensitic alloys a promising structural material for advanced nuclear reactors. [20] Oxide dispersion-strengthened (ODS) steel is one of the most prominent candidates as the fuel cladding or blanket component in advanced nuclear reactors. [21] According to a 2019 Congressional Research Services (CRS) report, Advanced Nuclear Reactors: Technology Overview and Current Issues, all nuclear power stations in the United States use light water reactors. [22] 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. [23] 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. [24] 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. [25] This result sheds light on the design of radiation-tolerant materials for advanced nuclear reactor applications. [26] An advanced nuclear reactor Generation IV, called Molten Salt Reactor (MSR), has been developed with Thorium utilization for a sustainable energy system. [27] 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. [28] 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. [29] 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. [30] %) ferritic/martensitic (F/M) steel is a candidate material for fuel cladding in advanced nuclear reactors. [31] 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. [32] Oxide dispersion strengthened (ODS) steels are being developed for fuel claddings in advanced nuclear reactors. [33] 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. [34] 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. [35] 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. [36] Advanced nuclear reactor concepts aim to use fuels that must withstand unprecedented temperature and radiation extremes. [37] High temperature-ultrafine precipitate strengthened (HT-UPS) steel has potential applications in advanced nuclear reactors as a structural material. [38] Several advanced nuclear reactor concepts have been proposed in the past few years where FLiBe molten salt represents a major constituent of the core. [39] 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. [40] 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. [41] Nevertheless, service temperature more than that temperature are one of the key feature of advanced nuclear reactors to gain higher thermal efficiency which is related to economic beneficial, and also to withstand from abnormal condition. [42] As an effective severe accident mitigation strategy, in-vessel retention – external reactor vessel cooling (IVR-ERVC) has been applied to some advanced nuclear reactors. [43] This study highlights the principles and importance of high-energy BM and SPS of Fe-9Cr model alloy for the future development of more complex oxide dispersion-strengthened alloys for various applications including advanced nuclear reactor applications. [44] Alloy 709 is an austenitic stainless steel with potential for structural applications in advanced nuclear reactors. [45] Passive cooling based on natural circulation is utilized in ex-vessel core catcher system of an advanced nuclear reactor to handle severe accident scenario. [46] Printed circuit heat exchanger (PCHE) is one of the leading candidates to be employed in advanced nuclear reactors and next generation concentrated solar power applications due to its compactness and capability for high-temperature, high-pressure applications with high effectiveness. [47] In the longer term, advanced nuclear reactors in the form of sodium cooled, molten salt cooled, and high temperature gas cooled reactors hold the promise of providing efficient electricity production, industrial heat for heavy industry as well as the generation of hydrogen for synthetic fuel. [48] Nanostructured ferritic alloys are considered as candidates for structural components in advanced nuclear reactors due to a high density of nano-oxides (NOs) and ultrafine grain sizes. [49] The potential role for advanced nuclear reactors in U. [50]우리의 임무는 개발도상국의 첨단 원자로 우선순위 지정을 위한 비율 분석에 의한 다중 목표 최적화(MULTIMOORA)의 확장을 개발하는 것이었습니다. [1] 고선량 조사에 노출되는 원자로용 공학적 재료는 다양한 방사선 손상을 일으켜 재료의 성능 저하를 초래하여 미래의 첨단 원자로에 재료의 적용을 심각하게 제한합니다. [2] 복잡성과 이질성이 증가하는 첨단 원자로 시스템의 출현으로 상세한 고충실도 중성자 분석이 필요했습니다. [3] 첨단 원자로를 위한 다양한 수동적 안전 시스템이 개발되었습니다. [4] 첨단 원자로의 시뮬레이션에서는 고정밀, 고효율 및 다중 물리 결합에 대한 편리성과 같은 요구 사항이 제시되고 있습니다. [5] nan [6] 공동의 형성 및 성장과 관련된 팽창은 첨단 원자로 개념에서 구조 재료에 대한 방사선 유발 분해 모드 중 가장 해로운 것 중 하나입니다. [7] 고급 원자로 설계 및 고급 연료 유형은 기존 원자로 및 연료와 비교할 때 사고 시나리오에서 환경적 영향을 줄일 수 있는 안전 기능을 제공합니다. [8] 소형 모듈식 및 첨단 원자로는 원자력 기술이 직면한 문제(특히 경제적 경쟁력, 사고 위험, 확산 및 폐기물 생성과의 연결)를 처리하는 잠재적인 방법으로 제안되었습니다. [9] 이 합금은 고급 원자로의 구조적 응용 분야에 관심이 있습니다. [10] 엔트로피 안정화 복합 재료의 개념은 극한 환경, 특히 고급 원자로에서 사용되는 획기적인 재료의 설계 및 엔지니어링에 대한 새로운 방향을 제시합니다. [11] 또한, 첨단 원자로 중 하나인 용융염 원자로에 대한 유체 유량의 영향과 실험적으로 루프 기하학의 효과에 대한 연구와 관련된 연구 데이터는 농축 목적으로 본 연구에서 제공됩니다. [12] FLiBe라고도 알려진 용융 리튬 테트라플루오로베릴레이트(Li2BeF4) 염은 LiF와 BeF2의 2:1 혼합물과 함께 용융 염 원자로 또는 고온 냉각된 불화물 염과 같은 첨단 원자로 설계에서 냉각제 및 용매로 제안되고 있습니다. 온도 반응기. [13] 나트륨 냉각 고속 원자로(SFR)는 전기 생산에 상업적으로 적용되는 고급 원자로 개념 중 하나입니다. [14] 고급 원자로를 위한 포괄적인 시스템 분석 코드로 설계된 SAS4A/SASSYS-1은 단상 자연 순환 거동을 포착하기 위한 물리 모델의 검증이 필요합니다. [15] 몇몇 고급 원자로 설계는 현재 원자로에 비해 효율성과 안전성 향상을 약속하지만 현재 ASME 코드 적격 재료 세트에 의해 제한됩니다. [16] 탄소 발자국을 줄이려는 열망은 에너지를 생산하는 첨단 원자로에 대한 상당한 관심을 불러일으키고 있습니다. [17] 방법 연구는 첨단 원자로의 전체 범위 제어실 연구 시뮬레이터에서 수행되었습니다. [18] 고밀도 계면을 가진 그래핀 강화 니켈 매트릭스 나노복합체는 잠재적인 조사 내성 때문에 첨단 원자로의 후보 물질로 권장됩니다. [19] 매력적인 기계적 특성과 보이드 팽창에 대한 우수한 내성으로 인해 페라이트/마르텐사이트 합금은 고급 원자로에 대한 유망한 구조 재료입니다. [20] ODS(Oxide Dispersion-Strengthened)강은 첨단 원자로에서 연료 피복재 또는 블랭킷 구성요소로 가장 눈에 띄는 후보 중 하나입니다. [21] 2019년 미 의회 연구 서비스(CRS) 보고서인 Advanced Nuclear Reactors: Technology Overview and Current Issues에 따르면 미국의 모든 원자력 발전소는 경수로를 사용합니다. [22] nan [23] nan [24] nan [25] nan [26] nan [27] nan [28] nan [29] nan [30] nan [31] nan [32] nan [33] nan [34] nan [35] nan [36] nan [37] nan [38] nan [39] nan [40] nan [41] 그럼에도 불구하고 그 온도보다 높은 사용온도는 경제성과 관련된 더 높은 열효율을 얻고 또한 비정상 조건에서 견딜 수 있는 첨단 원자로의 핵심 특징 중 하나이다. [42] 효과적인 중대사고 완화 전략으로 일부 고급 원자로에는 IVR-ERVC(In-vessel Retention - External Reactor Vessel Cooling)가 적용되었습니다. [43] 이 연구는 첨단 원자로 응용을 포함한 다양한 응용을 위한 보다 복잡한 산화물 분산 강화 합금의 미래 개발을 위한 Fe-9Cr 모델 합금의 고에너지 BM 및 SPS의 원리와 중요성을 강조합니다. [44] Alloy 709는 고급 원자로의 구조적 응용 가능성이 있는 오스테나이트계 스테인리스강입니다. [45] 자연 순환에 기반한 수동 냉각은 중대사고 시나리오를 처리하기 위해 첨단 원자로의 선박 외 노심 캐처 시스템에 활용됩니다. [46] 인쇄 회로 열 교환기(PCHE)는 고온, 고압 응용 분야를 고효율로 처리할 수 있는 소형 및 기능으로 인해 첨단 원자로 및 차세대 집중 태양광 발전 응용 분야에 사용되는 주요 후보 중 하나입니다. [47] 장기적으로 나트륨 냉각, 용융염 냉각 및 고온 가스 냉각 원자로 형태의 첨단 원자로는 효율적인 전력 생산, 중공업용 공업용 열 및 합성 연료용 수소 생성을 제공할 가능성이 있습니다. [48] 나노구조의 페라이트 합금은 고밀도의 나노산화물(NO)과 초미세 입자 크기로 인해 첨단 원자로의 구조 부품 후보로 간주됩니다. [49] 미국에서 첨단 원자로의 잠재적 역할 [50]
advanced nuclear power 첨단 원자력
In advanced nuclear power plant such as the AP1000 passive safety system, pool boiling is also used to fulfil the residual heat removal function through the Passive Residual Heat Removal Heat Exchanger (PRHR HX). [1] To reduce capital costs of advanced nuclear power plants and make commercial nuclear energy more competitive, innovations are needed in their structural design and construction, and not just in the reactor core and associated systems. [2] The Passive Residual Heat Removal Heat Exchanger (PRHR HX) is an important equipment of the passive safety system in advanced nuclear power plants such as AP1000. [3] The new correlation which adequately predicts the local variation of the nucleate boiling heat flux along the outer surface of the RPV under IVR-ERVC conditions can be used to describe the long-term cooling behavior of the corium within the RPV of advanced nuclear power plants. [4] Nuclear Regulatory Commission’s functional containment concept provides advanced nuclear power plant designers with more flexibility in terms of the civil/structural design if the appropriate set of barriers for prevention of radioactive material release exist. [5] For Japan, this meant control over its energy supplies and the status associated with advanced nuclear power technology. [6] The framework is applied to the case study of a generic Passive Safety System (PSS) for Decay Heat Removal (DHR) designed for advanced Nuclear Power Plants (NPPs). [7] NaCl–CaCl2 molten salt is considered as a promising high-temperature heat transfer and storage fluid for advanced nuclear power plants and concentrating solar power plants in the field of renewable energy utilization. [8] The projects of new advanced nuclear power units provide for their use in flexible load modes with a maximum unloading of up to 50% of the rated capacity. [9] Passive Safety Systems (PSSs) are increasingly employed in advanced Nuclear Power Plants (NPPs). [10] It is not only adopted as a backup operation mode during accidental scenarios but also as the normal operating mode in several small and medium-sized advanced nuclear power plants. [11] This work provides a fundamental guideline for the ECC system structure optimization and fatigue aging in the advanced nuclear power plants. [12] In order to anticipate station blackout, the use of safety system based on passive features is highly considered in advanced nuclear power plant designs, especially after the Fukushima Dai-ichi nuclear power station accident. [13] In advanced nuclear power plant AP1000, the passive residual heat removal heat exchanger (PRHR HX) is a key part of the passive safety system. [14] Since Gen III NPP, the passive safety system has been firstly used to enhance operational safety, develop reliability and performance of the advanced nuclear power plant. [15] The Secondary Circuit Passive Residual Heat Removal System (PRHRS) is designed for advanced nuclear power system. [16] The Secondary Circuit Passive Residual Heat Removal System (PRHRS) is designed for advanced nuclear power system. [17] The purpose of this study is to introduce a new and efficient virtual model-based ergonomic simulation framework utilizing recent anthropometric data for a digitalized main control room in an advanced nuclear power plant. [18] Passive safety system is the core feature of advanced nuclear power plant (NPP). [19] Therefore, having a deep understanding on the convective heat transfer characteristics of molten salts flowing in complex heat transfer structures is a critical issue to realize the high heat-transfer performance for new energy utilization technologies, especially the next-generation advanced nuclear power plant and high-temperature concentrated solar power (CSP) plant. [20] Advanced nuclear power plants are equipped with passive emergency heat removal systems (PEHRS) for removing the decay heat from reactor equipment in accidents accompanied by primary circuit leakage to the final heat absorber (ambient air). [21] ABSTRACT The increasing adoption of passive safety based front-line systems in advanced nuclear power reactors due to their simplicity, cost competitiveness and autonomous nature makes it very essential to carefully consider the uncertainties associated with their behaviour and the phenomena linked to their operations. [22]AP1000 수동안전시스템과 같은 첨단 원자력발전소에서는 PRHR HX(Passive Residual Residual Removal Heat Exchanger)를 통한 잔류열 제거 기능을 수행하기 위해 Pool Boiling도 사용됩니다. [1] 첨단 원자력 발전소의 자본 비용을 줄이고 상업용 원자력 에너지의 경쟁력을 높이려면 원자로 노심 및 관련 시스템뿐만 아니라 구조 설계 및 건설에 혁신이 필요합니다. [2] nan [3] IVR-ERVC 조건에서 RPV의 외부 표면을 따라 핵 끓는 열유속의 국부적 변화를 적절하게 예측하는 새로운 상관 관계는 고급 원자력 발전소의 RPV 내에서 노심의 장기 냉각 거동을 설명하는 데 사용할 수 있습니다. [4] nan [5] 일본에게 이것은 에너지 공급과 첨단 원자력 기술과 관련된 지위에 대한 통제를 의미했습니다. [6] nan [7] NaCl-CaCl2 용융염은 신재생에너지 활용 분야에서 첨단 원자력 발전소 및 집광 태양광 발전소의 유망한 고온 열전달 및 저장 유체로 간주됩니다. [8] nan [9] nan [10] nan [11] 본 연구는 첨단 원자력발전소의 ECC 계통구조 최적화 및 피로노화를 위한 기본 지침을 제공한다. [12] 스테이션 정전을 예측하기 위해, 특히 후쿠시마 다이이치 원자력 발전소 사고 이후 선진 원자력 발전소 설계에서 수동적 특징에 기반한 안전 시스템의 사용이 매우 고려됩니다. [13] 첨단 원자력 발전소 AP1000에서 수동 잔열 제거 열교환기(PRHR HX)는 수동 안전 시스템의 핵심 부분입니다. [14] 3세대 원전 이후 수동적 안전 시스템은 운전 안전성을 향상시키고 첨단 원자력 발전소의 신뢰성과 성능을 개발하기 위해 처음으로 사용되었습니다. [15] 2차 회로 수동 잔류 열 제거 시스템(PRHRS)은 고급 원자력 시스템용으로 설계되었습니다. [16] 2차 회로 수동 잔류 열 제거 시스템(PRHRS)은 고급 원자력 시스템용으로 설계되었습니다. [17] 본 연구의 목적은 첨단 원자력발전소의 디지털화된 주제어실에 대한 최근의 인체 측정 데이터를 활용한 새롭고 효율적인 가상 모델 기반 인체공학 시뮬레이션 프레임워크를 도입하는 것이다. [18] 수동적 안전 시스템은 첨단 원자력 발전소(NPP)의 핵심 기능입니다. [19] 따라서 복잡한 열전달 구조 내를 흐르는 용융염의 대류 열전달 특성에 대한 깊은 이해는 차세대 첨단 원자력 발전소 및 높은 열전달 신에너지 활용 기술, 특히 높은 열전달 성능을 구현하기 위한 중요한 문제입니다. - 온도 집중형 태양열 발전(CSP) 발전소. [20] nan [21] nan [22]
advanced nuclear energy 첨단 원자력 에너지
To evaluate the effects of irradiation on additive manufacturing materials which are expected to be applied in advanced nuclear energy systems, selective laser melting 316L stainless steel (SLM 316L SS) and traditionally manufactured 316L stainless steel (TM 316L SS), were irradiated with 500 keV He ions at 700°C, respectively. [1] In this study, we propose a novel concept of advanced nuclear energy system (ANES) for transmuting LLFPs efficiently without isotopic separation. [2] The world's nuclear energy community is exploring and developing advanced nuclear energy technology with a view to solving the economic, safety and environmental issues in the development of nuclear energy. [3] The neutron spectrum is one of the essential parameters in the design of advanced nuclear energy systems. [4] The Monte Carlo photon transport code IMPC-Photon is developed for serving the software development of designing advanced nuclear energy system such as Accelerator Driven Advanced Nuclear Energy System (ADANES) in Chinese Academy of Sciences. [5] The combined application of laser and optical fiber technologies has the potential to offer innovative measurement solutions that could accelerate research and development activities and improve the competitiveness of advanced nuclear energy system. [6] In 2006, the final report of the MIT Center for Advanced Nuclear Energy Center the project entitled High Performance Fuel Design for Next Generation PWR’s presented the proposal of an internal and external cooled ring fuel with the objective of increasing the power density of a PWR reactor without compromising the safety margins of the installation. [7] Candidate materials for advanced nuclear energy systems, i. [8] The Compact Materials Irradiation Facility (CMIF) project will provide a high-energy, high-flux neutron source for material irradiation research which will be indispensable for the long-term Accelerator-Driven Advanced Nuclear Energy (ADANE) project in China. [9] The formation of helium bubbles and the consequential property degradation are critical challenges for materials used in advanced nuclear energy systems. [10] Michal CIBULA1,*, Yusuke INABA1, Yongjie LI1, Tomoya SUZUKI2,*, Hirokazu NARITA2 and Kenji TAKESHITA1 1Laboratory for Advanced Nuclear Energy, Tokyo Institute of Technology, 2-12-1 Ookayama, Meguro-ku, Tokyo 152-8550, Japan; 2Environmental Management Research Institute, National Institute of Advanced Industrial Science and Technology (AIST), 16-1 Onogawa, Tsukuba, Ibaraki 305-8569, Japan (Received October 11, 2018; Accepted November 12, 2018). [11] For the structure materials applied in advanced nuclear energy system, helium bubble formation is always a big concern which will severely degrade the performance of materials around or above the half-melting temperature regime (∼0. [12] A project of Accelerator Driven Advanced Nuclear Energy System (ADANES) has been proposed in China. [13] In the search for new ways to generate carbon-free, reliable base-load power, interest in advanced nuclear energy technologies, particularly Molten Salt Reactors (MSRs), has resurged with multiple new companies pursuing MSR commercialization. [14] ADS is a key part of the accelerator-driven advanced nuclear energy system (ADANES), and its research and development (R&D) will play a very important role in promoting China’s energy transformation and stimulating the innovative development of China’s nuclear energy industry. [15] To access irradiation conditions of candidate materials used in advanced nuclear energy systems, simultaneous helium and iron-ion irradiation have been widely used to study on the synergistic effects of helium bubble nucleation and displacement damage. [16] The need for enhanced radiation-tolerant materials for advanced nuclear energy designs has resulted in a growing number of investigations that have explored the effect of grain boundaries under irradiation. [17] This paper reviews some of the fuels and structural materials used in advanced nuclear energy systems and identifies promising candidates for these systems. [18]첨단 원자력 시스템에 적용될 것으로 예상되는 적층 제조 재료에 대한 조사의 영향을 평가하기 위해 선택적 레이저 용융 316L 스테인리스강(SLM 316L SS) 및 전통적으로 제조된 316L 스테인리스강(TM 316L SS)에 500 keV를 조사했습니다. 그는 각각 700°C에서 이온화됩니다. [1] 이 연구에서 우리는 동위원소 분리 없이 LLFP를 효율적으로 변환하기 위한 ANES(Advanced 원자력 에너지 시스템)의 새로운 개념을 제안합니다. [2] nan [3] 중성자 스펙트럼은 첨단 원자력 시스템 설계의 필수 매개변수 중 하나입니다. [4] Monte Carlo 광자 전송 코드 IMPC-Photon은 중국과학원의 ADANES(가속기 구동 첨단 원자력 시스템)와 같은 첨단 원자력 시스템 설계 소프트웨어 개발을 위해 개발되었습니다. [5] nan [6] nan [7] 첨단 원자력 시스템용 후보 물질, i. [8] CMIF(Compact Materials Irradiation Facility) 프로젝트는 중국의 장기 가속기 구동 첨단 원자력(ADANE) 프로젝트에 필수 불가결한 물질 조사 연구를 위한 고에너지, 고유속 중성자 소스를 제공할 것입니다. [9] 헬륨 기포의 형성과 그에 따른 특성 저하가 첨단 원자력 시스템에 사용되는 재료의 중요한 문제입니다. [10] Michal CIBULA1,*, Yusuke INABA1, Yongjie LI1, Tomoya SUZUKI2,*, Hirokazu NARITA2 및 Kenji TAKESHITA1 1첨단 원자력 에너지 연구소, Tokyo Institute of Technology, 2-12-1 Ookayama, Meguro-ku, Tokyo 152-8550, Japan 2환경 경영 연구소, 국립 산업 과학 기술 연구소(AIST), 16-1 Onogawa, Tsukuba, Ibaraki 305-8569, Japan(2018년 10월 11일 접수, 2018년 11월 12일 접수). [11] 첨단 원자력 에너지 시스템에 적용되는 구조 재료의 경우, 헬륨 기포 형성은 항상 반용융 온도 영역(~0.00~0.000) 주변 또는 그 이상에서 재료의 성능을 심각하게 저하시키는 큰 문제입니다. [12] 가속기 구동 첨단 원자력 시스템(ADANES) 프로젝트가 중국에서 제안되었습니다. [13] nan [14] nan [15] nan [16] nan [17] nan [18]
advanced nuclear system 첨단 원자력 시스템
Developing long-lifetime bulk-form ceramic-based materials with high irradiation resistance is crucial for advanced nuclear systems. [1] ” In particular, the RFP called for the prime contractor to “develop the capability to model and simulate advanced nuclear systems from the microscopic to the macroscopic level, enabling advanced experimentation involving Generation IV technologies. [2] Heat-pipes naturally fit these requirements and are being investigate for use in advanced nuclear systems. [3] The radiation safety design and emergency analysis of an advanced nuclear system highly depends on the source term analysis results. [4] The intricate balance between reactor economics and safety necessitates the emergence of new and advanced nuclear systems and, very importantly, advanced materials, which can overcome current shortcomings and bring about more economic nuclear systems with designed-in inherent safety features. [5] Helium accumulation in advanced nuclear systems would accelerate the failure of structural materials. [6] To provide a basic understanding of the synergy effect of hydrogen and helium on structural materials for future advanced nuclear systems, the vacancy-type defects in SIMP steel induced by separate and sequential H and He implantation at room temperature was investigated using positron annihilation Doppler broadening spectroscopy (DBS) and transmission electron microscopy (TEM). [7] The NEAMS IPL will enable users to apply highfidelity simulations to inform lowerorder models for the design, analysis, and licensing of advanced nuclear systems. [8] Reduced-activation Fe-Mn-Cr alloys have been regarded as the candidate structural materials for advanced nuclear systems. [9] In advanced nuclear systems, the service environment of core components is quite different from that of traditional nuclear systems, and the corresponding materials need to withstand much higher temperatures and higher flux neutron irradiation. [10] In advanced nuclear systems, especially hybrid nuclear systems, long-lived high-level radionuclides in nuclear wastes can be converted into short-lived nuclides or stable nuclides via nuclear waste transmutation. [11] There are complicated features for advanced nuclear systems, such as the complex neutron spectrum and angular distribution, complicated material composition, large spatial span, complex geometry, etc. [12] Advanced nuclear systems have the characteristics of complex neutron spectra and angular distribution, complex material composition, and extreme multi-physics coupling. [13] The numerical modeling of this problem has attracted considerable attention from researchers because it has practical applications in biological sciences, electronic cooling, advanced nuclear systems, etc. [14] In this work, two high-temperature hydrogen production methods coupled with an advanced nuclear system are presented. [15] Lead bismuth eutectic (LBE) alloy shows high potential for application in advanced nuclear systems such as lead-alloy-cooled fast reactors. [16] Understanding the irradiation hardening effect of structural steels under various irradiation conditions plays an important role in developing advanced nuclear systems. [17] The accurate knowledge of neutron cross-sections of a variety of plutonium isotopes and other minor actinides, such as neptunium, americium and curium, is crucial for feasibility and performance studies of advanced nuclear systems (Generation-IV reactors, Accelerator Driven Systems). [18]방사선 저항성이 높은 수명이 긴 벌크 형태의 세라믹 기반 재료를 개발하는 것은 첨단 원자력 시스템에 매우 중요합니다. [1] 특히 RFP는 주 계약자가 "미시 수준에서 거시 수준까지 고급 핵 시스템을 모델링하고 시뮬레이션할 수 있는 기능을 개발하여 4세대 기술과 관련된 고급 실험을 가능하게 하는 능력을 개발할 것을 요구했습니다. [2] 히트 파이프는 이러한 요구 사항에 자연스럽게 부합하며 첨단 원자력 시스템에 사용하기 위해 조사되고 있습니다. [3] 선진원자력시스템의 방사선안전설계 및 비상해석은 선원항해석 결과에 크게 의존한다. [4] 원자로 경제성과 안전 사이의 복잡한 균형은 새롭고 진보된 원자력 시스템의 출현을 필요로 하며, 매우 중요하게는 현재의 단점을 극복하고 설계된 고유의 안전 기능을 갖춘 보다 경제적인 원자력 시스템을 가져올 수 있는 첨단 재료의 출현을 필요로 합니다. [5] nan [6] 미래 첨단 원자력 시스템의 구조 재료에 대한 수소와 헬륨의 시너지 효과에 대한 기본 이해를 제공하기 위해 상온에서 분리되고 순차적인 H 및 He 주입에 의해 유도된 SIMP 강철의 공공형 결함을 양전자 소멸 도플러 확장 분광법을 사용하여 조사했습니다. (DBS) 및 투과 전자 현미경(TEM). [7] NEAMS IPL을 통해 사용자는 고충실도 시뮬레이션을 적용하여 고급 원자력 시스템의 설계, 분석 및 라이센스를 위한 하위 모델에 정보를 제공할 수 있습니다. [8] 환원 활성화 Fe-Mn-Cr 합금은 첨단 원자력 시스템의 후보 구조 재료로 간주되어 왔습니다. [9] 첨단 원자력 시스템에서 핵심 구성 요소의 서비스 환경은 기존 원자력 시스템의 서비스 환경과 상당히 다르며 해당 재료는 훨씬 더 높은 온도와 더 높은 플럭스 중성자 조사를 견뎌야 합니다. [10] 첨단 핵 시스템, 특히 하이브리드 핵 시스템에서 핵폐기물의 장수명 고준위 방사성 핵종은 핵폐기물 변환을 통해 단수명 핵종 또는 안정 핵종으로 전환될 수 있습니다. [11] 복잡한 중성자 스펙트럼 및 각도 분포, 복잡한 재료 구성, 큰 공간 범위, 복잡한 기하학 등과 같은 고급 핵 시스템에는 복잡한 기능이 있습니다. [12] 고급 핵 시스템은 복잡한 중성자 스펙트럼과 각도 분포, 복잡한 재료 구성 및 극단적인 다중 물리학 결합의 특성을 가지고 있습니다. [13] 이 문제의 수치 모델링은 생물학, 전자 냉각, 첨단 핵 시스템 등에 실용적인 응용이 있기 때문에 연구자들의 상당한 관심을 끌었습니다. [14] nan [15] nan [16] nan [17] nan [18]