Researching | Development and validation of a thermal-hydraulic analysis code for dual cooled assemblies in molten salt reactors

NUCLEAR TECHNIQUES, Volume. 47, Issue 9, 090602(2024)

Development and validation of a thermal-hydraulic analysis code for dual cooled assemblies in molten salt reactors

Siqin HU1...2, Chong ZHOU1,2,*, Guifeng ZHU1,2, Yang ZOU1,2, Xiaohan YU1,2, and Shuaiyu XUE12 |Show fewer author(s)

Author Affiliations

¹Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China

²University of Chinese Academy of Sciences, Beijing 100049, China

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References(22)

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Siqin HU, Chong ZHOU, Guifeng ZHU, Yang ZOU, Xiaohan YU, Shuaiyu XUE. Development and validation of a thermal-hydraulic analysis code for dual cooled assemblies in molten salt reactors[J]. NUCLEAR TECHNIQUES, 2024, 47(9): 090602

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Paper Information

Category: NUCLEAR ENERGY SCIENCE AND ENGINEERING

Received: Nov. 16, 2023

Accepted: --

Published Online: Nov. 13, 2024

The Author Email:

DOI:10.11889/j.0253-3219.2024.hjs.47.090602

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