Code development and preliminary validation for lead-cooled fast reactor thermal-hydraulic transient behavior-Reference-Cited by-同舟云学术

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Code development and preliminary validation for lead-cooled fast reactor thermal-hydraulic transient behavior

Published:2024-06 Issue:6 Volume:56 Page:2332-2342
ISSN:1738-5733
Container-title:Nuclear Engineering and Technology
language:en
Short-container-title:Nuclear Engineering and Technology

Author:

Wang Chenglong^ORCID,Wang Chen,Tian Wenxi,Su Guanghui,Qiu Suizheng

Publisher

Elsevier BV

Reference20 articles.

1. GEN-IV LFR development: status & perspectives;Lorusso;Prog. Nucl. Energy,2018

2. Mixed convection and stratification phenomena in a heavy liquid metal pool;Tarantino;Nucl. Eng. Des.,2015

3. Heavy liquid metal natural circulation in a one-dimensional loop;Coccoluto;Nucl. Eng. Des.,2011

4. Natural circulation in a liquid metal one-dimensional loop;Tarantino;J. Nucl. Mater.,2008

5. Transient experiments from the thermal-hydraulic ADS lead bismuth loop (TALL) and comparative TRAC/AAA analysis;Ma;Nucl. Eng. Des.,2006

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