Prediction of critical heat flux in rod bowing geometries by coupled subchannel analysis and mechanistic model-Reference-Cited by-同舟云学术

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Prediction of critical heat flux in rod bowing geometries by coupled subchannel analysis and mechanistic model

Published:2024-06 Issue: Volume:200 Page:110401
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Guo Junliang,Shan Jianqiang,Jiang Li,Peng Yujiao,Zhou Shan,Gui Miao

Funder

National Key Research and Development Program of China

Shanghai Nuclear Engineering Research and Design Institute

National Natural Science Foundation of China

Xi’an Jiaotong University

Publisher

Elsevier BV

Reference25 articles.

1. Structural Mechanics;Cain,1990

2. On the definition of critical heat flux margin;Groeneveld;Nucl. Eng. Des.,1996

3. The 2006 CHF look-up table;Groeneveld;Nucl. Eng. Des.,2007

4. Fluid-to-Fluid modelling of CHF at High-Pressure subcooled water conditions;Guo;Nucl. Eng. Des.,2022

5. Effect of a rod bowed to contact on critical heat-flux in pressurized water-reactor rod bundles;Hill;Mech. Eng.,1976

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