Development a methodology for evaluating inter‐assembly heat transfer effect through reactor core in system safety analysis of sodium‐cooled fast reactor-Reference-Cited by-同舟云学术

Development a methodology for evaluating inter‐assembly heat transfer effect through reactor core in system safety analysis of sodium‐cooled fast reactor

Published:2021-01-20 Issue:8 Volume:45 Page:12258-12271
ISSN:0363-907X
Container-title:International Journal of Energy Research
language:en
Short-container-title:Int J Energy Res

Author:

Wang Shibao¹²^ORCID,Zhang Dalin¹²^ORCID,Liang Yu¹²,Wang Xinan¹²,Qiu Suizheng¹²,Su Guanghui¹²,Tian Wenxi¹²

Affiliation:

1. State Key Laboratory of Multiphase Flow in Power Engineering; Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology Xi'an Jiaotong University Xi'an P. R. China

2. School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an P. R. China

Funder

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.6369

Reference29 articles.

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4. A porous body model for predicting temperature distribution in wire-wrapped rod assemblies operating in combined forced and free convection

5. Transient experiments on fast reactor core thermal-hydraulics and its numerical analysis

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