An experiment‐based validation of a system code for prediction of passive natural circulation in sodium‐cooled fast reactor-Reference-Cited by-同舟云学术

An experiment‐based validation of a system code for prediction of passive natural circulation in sodium‐cooled fast reactor

Published:2020-10-27 Issue:8 Volume:45 Page:12093-12109
ISSN:0363-907X
Container-title:International Journal of Energy Research
language:en
Short-container-title:Int J Energy Res

Author:

Wang Shibao¹^ORCID,Zhang Dalin¹^ORCID,Liu Yapeng¹,Wang Chenglong¹^ORCID,Qiu Suizheng¹,Su Guanghui¹,Tian Wenxi¹

Affiliation:

1. State Key Laboratory of Multiphase Flow in Power Engineering; Shaanxi Key Lab. of Advanced Nuclear Energy and Technology; School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an Shaanxi 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.6103

Reference12 articles.

1. Basic verification of THACS for sodium-cooled fast reactor system analysis

2. Thermal‐hydraulic analysis of EBR‐II shutdown heat removal tests SHRT‐17 and SHRT‐45R;Yue N;Prog Nucl Energy,2015

3. The development and validation of the inter-wrapper flow model in sodium-cooled fast reactors

4. Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors

5. Validation of a methodology for thermal stratification analysis in sodium-cooled fast reactors

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