Simulation study on thermal characteristics of primary coolant system of lead-bismuth cooled reactor-Reference-Cited by-同舟云学术

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Simulation study on thermal characteristics of primary coolant system of lead-bismuth cooled reactor

Published:2022-09 Issue:3 Volume:4 Page:139-146
ISSN:2468-6050
Container-title:International Journal of Advanced Nuclear Reactor Design and Technology
language:en
Short-container-title:International Journal of Advanced Nuclear Reactor Design and Technology

Author:

Lu Shuaijie^ORCID,Peng Minjun,Xia Genglei,Zhang Qianping

Publisher

Elsevier BV

Subject

General Medicine

Reference30 articles.

1. Nuclear power development in market conditions with use of multi-purpose modular fast reactors SVBR-75/100;Zrodnikov;Nucl. Eng. Des.,2006

2. Innovations in the ENHS reactor design and fuel cycle;Greenspan;Prog. Nucl. Energy,2008

3. PbBi-cooled direct contact boiling water small reactor;Takahashi;Prog. Nucl. Energy,2005

4. URANUS: Korean lead-bismuth cooled small modular fast reactor activities;Choi,2011

5. Design and R&D progress of China lead-based reactor for ADS research facility;Wu;Engineering,2016

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