Alloy E110(合金E110)研究综述
Alloy E110 合金E110 - Calculations also showed that chromium metal has a greater stopping power compared to the zirconium-based alloy E110, which indicates an increased ability of chromium to withstand exposure to energetic fission fragments during reactor operation. [1] Reorientation of hydrides in the course of dry storage of spent nuclear fuel is a possible mechanism for the degradation of the properties of fuel claddings made of alloy E110 (Zr–1% Nb) based on spongy zirconium in VVER reactors. [2] This correlation allows for the statement on a reasonable basis that the [NH3]/[H2] ratio in the primary coolant of transport nuclear units is a fair indicator of the fact of general corrosion of zirconium alloys in the core having a structural member made of alloy E110. [3] It is also shown in this work that the threshold dose for the formation of -type dislocation loops in alloy E110 (under the specified irradiation conditions) does not exceed 5. [4] —The structure and properties of the surface layers of samples of alloy E110 (Zr–1 wt % Nb) have been studied after high-speed laser dispersion of powders of magnesium oxide and titanium dioxide. [5]计算还表明，与锆基合金 E110 相比，铬金属具有更大的阻止能力，这表明铬在反应堆运行期间承受暴露于高能裂变碎片的能力有所提高。 [1] 在乏核燃料干式储存过程中氢化物的重新定向是 VVER 反应堆中由基于海绵状锆的合金 E110 (Zr–1% Nb) 制成的燃料包壳性能退化的一种可能机制。 [2] 这种相关性允许在合理的基础上做出这样的陈述，即运输核装置的一次冷却剂中的 [NH3]/[H2] 比率是具有由合金 E110。 [3] 在这项工作中还表明，在合金 E110 中形成-型位错环的阈值剂量（在指定的辐照条件下）不超过 5。 [4] —研究了高速激光分散氧化镁和二氧化钛粉末后，合金 E110 (Zr–1 wt % Nb) 样品表层的结构和性能。 [5]
Zirconium Alloy E110 锆合金 E110
The features of oxidation and hydrogenation of zirconium alloy E110 under electron and plasma irradiation in various conditions are studied. [1] Three directions of the establishment of accident tolerant fuel cladding for light water reactors are actively exploring at present: 1) replacement zirconium alloy E110 for more corrosion-resistant material in accident operation conditions; 2) surface dispersion hardening or doping of the zirconium cladding of fuel element; 3) deposition a corrosion-resistant coating to the fuel cladding. [2] The issue presents the results of studies of methods for increasing the corrosion resistance of fuel claddings made from zirconium alloy E110, performed at the SRC RF TRINITI, using coatings (Al, Al2O3, Cr) by pulsed laser deposition, as well as magnetron sputtering and galvanic deposition of chromium. [3] In this work, the results of the irradiation of untreated, preliminarily Ar+-bombarded and Cr-coated samples of zirconium alloy E110 (Zr-1%Nb) with deuterium atoms and ions of deuterium plasma were compared with the results of their exposure to superheated water steam (673 K, 11 MPa; 673 K, 0. [4] In the present study the Nd:YAG pulsed laser welding of zirconium alloy E110 was simulated using three-dimensional heat and fluid flow model. [5] This paper describes the influence of silicon carbide (SiC) coating on hydrogen sorption kinetics of zirconium alloy E110 (Zr-1Nb). [6]研究了锆合金E110在不同条件下电子和等离子体辐照下的氧化和氢化特性。 [1] 目前正在积极探索建立轻水堆耐事故燃料包壳的三个方向：1）将锆合金E110替换为事故运行条件下更耐腐蚀的材料； 2）燃料元件锆包壳的表面弥散硬化或掺杂； 3) 在燃料包壳上沉积一层耐腐蚀涂层。 [2] 本期介绍了提高由锆合金 E110 制成的燃料包壳的耐腐蚀性的方法研究结果，该方法在 SRC RF TRINITI 进行，使用脉冲激光沉积涂层（Al、Al2O3、Cr）以及磁控溅射和铬的电镀沉积。 [3] 在这项工作中，用氘原子和氘等离子体离子辐照未处理、初步 Ar+ 轰击和 Cr 涂层的锆合金 E110 (Zr-1%Nb) 样品的结果与它们暴露于过热的结果进行了比较。水蒸汽（673 K，11 MPa；673 K，0。 [4] 在本研究中，采用三维热和流体流动模型模拟了锆合金 E110 的 Nd:YAG 脉冲激光焊接。 [5] 本文介绍了碳化硅 (SiC) 涂层对锆合金 E110 (Zr-1Nb) 吸氢动力学的影响。 [6]