Improvement and validation of a sub‐channel analysis code for a lead‐cooled reactor with wire spacers-Reference-Cited by-同舟云学术

Improvement and validation of a sub‐channel analysis code for a lead‐cooled reactor with wire spacers

Published:2020-10-15 Issue:8 Volume:45 Page:12029-12046
ISSN:0363-907X
Container-title:International Journal of Energy Research
language:en
Short-container-title:Int J Energy Res

Author:

Wu Di¹^ORCID,Wang Chenglong¹^ORCID,Gui Minyang¹,Lan Zhike²,Lu Qi²,Zhang Dalin¹^ORCID,Tian Wenxi¹,Qiu Suizheng¹,Su Guanghui H.¹

Affiliation:

1. School of Nuclear Science and Technology, Shanxi Key Laboratory of Advanced Nuclear Energy and Technology, State Key Laboratory of Multiphase Flow in Power Engineering Xi'an Jiaotong University Xi'an China

2. Nuclear Power Institute of China Chengdu China

Funder

National Natural Science Foundation of China

National Key Research and Development Program 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.6015

Reference42 articles.

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2. Transient thermal-hydraulic evaluation of lead-bismuth fast reactor by coupling sub-channel and system analysis codes

3. A subchannel analysis code MATRA-LMR for wire wrapped LMR subassembly

4. Development of a sub‐channel code for liquid metal cooled fuel assembly;Liu X;Ann Nucl Energy,2015

5. A sub-channel analysis code for advanced lead bismuth fast reactor

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