CorTAF-LBE: A full scale subchannel-level thermal-hydraulic characteristics analysis code for LBR core based on OpenFOAM-Reference-Cited by-同舟云学术

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CorTAF-LBE: A full scale subchannel-level thermal-hydraulic characteristics analysis code for LBR core based on OpenFOAM

Published:2024-08 Issue: Volume:173 Page:105259
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Liu Kai^ORCID,Yu Jiacheng,Qiu Hanrui,Wang Mingjun,Tian Wenxi,Su G.H.

Funder

CNNC

Publisher

Elsevier BV

Reference29 articles.

1. Developmental assessment of RELAP5/MOD3.1 with separate effect and integral test experiments: model changes and options;Analytis;Nucl. Eng. Des.,1996

2. CFD analysis of flow blockage phenomena in a LBE-cooled 19-pin wire-wrapped rod bundle;Chai;Nucl. Eng. Des.,2019

3. CFD analysis of thermal–hydraulic behavior of heavy liquid metals in sub-channels;Cheng;Nucl. Eng. Des.,2006

4. Numerical simulation on the thermal stratification in the lead pool of lead-cooled fast reactor (LFR);Dong;Ann. Nucl. Energy,2022

5. Numerical prediction of flow and heat transfer in an infinite wire-wrapped fuel assembly;Dovizio;Nucl. Eng. Des.,2019

Cited by 2 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. Thermal-hydraulic analysis of a full-scale lead-bismuth cooled fast reactor core considering inter-wrapper flow;Progress in Nuclear Energy;2024-10

2. Application of BPNN algorithm in thermal-hydraulic analysis of unwrapped LFR core;International Journal of Thermal Sciences;2024-09

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