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Investigation of the Safety Features of Advanced PWR Assembly Using SiC, Zr, FeCrAl and SS-310 As Cladding Materials

机译：使用SiC，Zr，Fecral和SS-310作为包层材料的高级PWR组件安全特征研究

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Sayed Mustafa;
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1. Reactor Physics Implications of Advanced SiC-clad Fuel in PWRs [J] . D. Bloore, K. Shirvan, E. E. Pilat, Transactions of the American nuclear society . 2014,第nova期

机译：压水堆中先进SiC包覆燃料的反应堆物理意义
2. Evolutionary developments of advanced PWR nuclear fuels and cladding materials [J] . Kyu-Tae Kim Nuclear Engineering and Design . 2013,第octa期

机译：先进压水堆核燃料和包壳材料的进化发展
3. Preliminary Risk Analysis of FeCrAl Cladding Design Impact on a Generic PWR Station Blackout PRA Model [J] . Zhegang Ma, Carlo Parisi, Hongbin Zhang, Transactions of the American nuclear society . 2018,第Nova期

机译：FeCrAl覆层设计对一般PWR站停电PRA模型影响的初步风险分析
4. The effects of SiC cladding thickness on advanced PWR fuel rod performance [C] . Yanin Sukjai, Koroush Shirvan, Edward Pilat, International congress on advances in nuclear power plants . 2014

机译：SiC包层厚度对先进PWR燃料棒性能的影响
5. High-Temperature Deformation Characteristics of Cladding Materials for Nuclear Reactors: HANA-4 and FeCrAl [D] . Joshi, Pratik. 2019

机译：核反应堆覆层材料的高温变形特性：Hana-4和群体
6. Biocompatible Materials Based on Self-Assembling Peptides on Ti25Nb10Zr Alloy: Molecular Structure and Organization Investigated by Synchrotron Radiation Induced Techniques [O] . Valeria Secchi, Stefano Franchi, Marta Santi, 2018

机译：基于Ti25Nb10Zr合金上自组装肽的生物相容性材料：同步辐射诱导技术研究的分子结构和组织
7. Report on Design and Failure Limits of SiC/SiC and FeCrAl ATF Cladding Concepts under RIA [O] . Mahmut N. Cinbiz, Nick Brown, Rick R. Lowden, 2018

机译：RIA下SIC / SIC和Fecral ATF覆盖概念的设计和失败限制报告

Investigation of the Safety Features of Advanced PWR Assembly Using SiC, Zr, FeCrAl and SS-310 As Cladding Materials

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