Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident conditions-Reference-Cited by-同舟云学术

登录注册会员服务联系我们

Preliminary safety analysis of the PWR with accident-tolerant fuels during severe accident conditions

Published:2015-06 Issue: Volume:80 Page:1-13
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Wu Xiaoli,Li Wei,Wang Yang,Zhang Yapei,Tian Wenxi,Su Guanghui,Qiu Suizheng,Liu Tong,Deng Yongjun,Huang Heng

Funder

National Nature Science Foundation of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference16 articles.

1. Silicon Carbide Oxidation in High Temperature Steam;Arnold,2011

2. Selection of fuel cladding material for nuclear fission reactors;Azevedo;Eng. Fail. Anal.,2011

3. Oxidation of fuel cladding candidate materials in steam environments at high temperature and pressure;Cheng;J. Nucl. Mater.,2012

4. CNPRI, 1999. Final Safety Analysis Report (FSAR) for Daya Bay Nuclear Power Station Unit 1 and 2. D-TD/GNPS/001.

5. Hohorst, J.K., 1990. SCDAP/RELAP5/MOD2 code manual, vol. 4: MATPRO–a library of materials properties for light-water-reactor accident analysis. EG&G Idaho Report NUREG/CR, 5273.

Cited by 41 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. A comprehensive examination of the linear and numerical stability aspects of the bubble collision model in the TRACE-1D two-fluid model applied to vertical disperse flow in a PWR core channel under loss of coolant accident conditions;Nuclear Engineering and Technology;2024-08

2. Degradation of the Cr2O3 layer protectiveness caused by grain refinement during high-temperature oxidation of Cr coatings;Materials Today Communications;2024-03

3. Review of Neutronics, Thermal-Hydraulic, and Fuel Performance Research of Accident Tolerant Fuels for APR-1400 in United Arab Emirates Nuclear Power Plants;Lecture Notes in Mechanical Engineering;2024

4. Accident tolerant fuels behavior analysis for Pressurized Water reactor in steady state and transient conditions;Nuclear Engineering and Design;2023-12

5. The effects of cladding thermo-physical and thermo-chemical properties on the coping time during a PWR unmitigated LB-LOCA;Progress in Nuclear Energy;2023-08

同舟云学术

1.学者识别学者识别

2.学术分析学术分析

3.人才评估人才评估

"同舟云学术"是以全球学者为主线，采集、加工和组织学术论文而形成的新型学术文献查询和分析系统，可以对全球学者进行文献检索和人才价值评估。用户可以通过关注某些学科领域的顶尖人物而持续追踪该领域的学科进展和研究前沿。经过近期的数据扩容，当前同舟云学术共收录了国内外主流学术期刊6万余种，收集的期刊论文及会议论文总量共计约1.5亿篇，并以每天添加12000余篇中外论文的速度递增。我们也可以为用户提供个性化、定制化的学者数据。欢迎来电咨询！咨询电话：010-8811{复制后删除}0370

www.globalauthorid.com

TOP

Copyright © 2019-2024 北京同舟云网络信息技术有限公司
京公网安备11010802033243号京ICP备18003416号-3