Development and validation of transient thermal‐hydraulic evaluation code for a lead‐based fast reactor-Reference-Cited by-同舟云学术

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Development and validation of transient thermal‐hydraulic evaluation code for a lead‐based fast reactor

Published:2021-01-03 Issue:8 Volume:45 Page:12215-12233
ISSN:0363-907X
Container-title:International Journal of Energy Research
language:en
Short-container-title:Int J Energy Res

Author:

Wei Shiying¹²^ORCID,Ma Weimin³,Wang Chenglong¹²^ORCID,Chen Ronghua¹²,Tian Wenxi¹²,Qiu Suizheng¹²,Su G. H.¹²

Affiliation:

1. Department of Nuclear Science and Technology Xi'an Jiaotong University Xi'an China

2. Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology Xi'an Jiaotong University Xi'an China

3. Nuclear Power Safety, School of Engineering Science Royal Institute of Technology (KTH) Stockholm Sweden

Funder

China Scholarship Council

National Key Research and Development Program of China

National Natural Science Foundation of China

Publisher

Wiley

Subject

Energy Engineering and Power Technology,Fuel Technology,Nuclear Energy and Engineering,Renewable Energy, Sustainability and the Environment

Link

https://onlinelibrary.wiley.com/doi/pdf/10.1002/er.6334

Reference42 articles.

1. GEN‐IV LFR development: status & perspectives;Lorusso P;Prog Nucl Energy,2018

2. Safety design of Pb–Bi-cooled direct contact boiling water fast reactor (PBWFR)

3. Safety analysis of small long life CANDLE fast reactor

4. Transient accident analysis of a supercritical carbon dioxide Brayton cycle energy converter coupled to an autonomous lead‐cooled fast reactor;Moisseytsev A;Nucl Eng Des,2008

5. Code development on steady-state thermal-hydraulic for small modular natural circulation lead-based fast reactor

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. Effect analysis of oxide layer on thermal hydraulic characteristics of LBE cooled reactor;Annals of Nuclear Energy;2024-08

2. UTOP accident analysis and mitigation measures of lead-cooled fast reactor considering coupling effect with SCO2 Brayton cycle;Progress in Nuclear Energy;2023-12

3. Liquid metal cooled fast reactor thermal hydraulic research development: A review;Heliyon;2023-06

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