Core design and neutronic study on small reactor with advanced fuel designs-Reference-Cited by-同舟云学术

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Core design and neutronic study on small reactor with advanced fuel designs

Published:2021-12 Issue: Volume:29 Page:101068
ISSN:2352-1791
Container-title:Nuclear Materials and Energy
language:en
Short-container-title:Nuclear Materials and Energy

Author:

Zhang Zhaozhan,Wu Tianfan,Wang Yujing,Chen Shengli,Yuan Cenxi,Zhu Jianyu

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,Materials Science (miscellaneous),Nuclear and High Energy Physics

Reference44 articles.

1. Looking ahead at reactor development;Magwood;Prog. Nucl. Energy,2018

2. Neutronics and fuel performance evaluation of accident tolerant FeCrAl cladding under normal operation conditions;Wu;Ann. Nucl. Energy,2015

3. Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors;George;Ann. Nucl. Energy,2015

4. Neutronic analysis for accident tolerant cladding candidates in CANDU-6 reactors;Naceur;Ann. Nucl. Energy,2018

5. Multidimensional multiphysics simulation of nuclear fuel behaviors;Williamson;J. Nucl. Mater.,2012

Cited by 3 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Neutron-physical characteristics of UO2 and UN/U3Si2 fuels with Zr, SiC and APMT accident tolerant claddings;Radiation Physics and Chemistry;2024-09

2. Neutronic investigation of prospective dual-cooled micro-heterogeneous duplex fuel for small modular long-life reactors: Assembly level design and analysis;Progress in Nuclear Energy;2023-06

3. Assessment of gadolinium concentration effects on the NuScale reactor parameters and optimizing the fuel composition via machine learning method;International Journal of Energy Research;2022-02-22

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