Preliminary development and verification of an OpenFOAM-based multi-physics coupling safety analysis code for Lead-based reactor

Author:

Ou Wenlan,Gong Zhengyu,Gu Zhixing,Pan Qiwen,Zhang Ling,Dai Jianing

Funder

National Natural Science Foundation of China

Science and Technology Department of Sichuan Province

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference28 articles.

1. Overview of lead-cooled fast reactor activities;Alemberti;Prog. Nucl. Energy,2014

2. Overview of leadcooled fast reactor activities;Alemberti;Prog. Nucl. Energy,2014

3. Towards more efficient implementations of multiscale thermal-hydraulics;Antoine;Nucl. Eng. Des.,2021

4. A multi-physics time-dependent model for the Lead Fast Reactor single-channel analysis;Aufiero;Nucl. Eng. Des.,2013

5. Development of an SP3 neutron transport solver for the analysis of the Molten Salt Fast Reactor;Aufiero;Chem. Eng. Sci.,2014

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