Thermal-hydraulic analysis of a full-scale lead-bismuth cooled fast reactor core considering inter-wrapper flow-Reference-Cited by-同舟云学术

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Thermal-hydraulic analysis of a full-scale lead-bismuth cooled fast reactor core considering inter-wrapper flow

Published:2024-10 Issue: Volume:175 Page:105331
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

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

Publisher

Elsevier BV

Reference26 articles.

1. MYRRHA–A multi-purpose fast spectrum research reactor;Abderrahim;Energy Convers. Manag.,2012

2. Overview of lead-cooled fast reactor activities[J];Alemberti;Prog. Nucl. Energy,2014

3. OpenFOAM for computational fluid dynamics[J];Chen;Notices of the AMS,2014

4. Heat transfer on HLM cooled wire-spaced fuel pin bundle simulator in the NACIE-UP facility [J];Di Piazza;Nucl. Eng. Des.,2016

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

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