A Review of Molten Salt Reactor Multi-Physics Coupling Models and Development Prospects

Author:

Wu JianhuiORCID,Chen Jingen,Cai Xiangzhou,Zou Chunyan,Yu Chenggang,Cui YongORCID,Zhang Ao,Zhao Hongkai

Abstract

Molten salt reactors (MSRs) are one type of GEN-IV advanced reactors that adopt melt mixtures of heavy metal elements and molten salt as both fuel and coolant. The liquid fuel allows MSRs to perform online refueling, reprocessing, and helium bubbling. The fuel utilization, safety, and economics can be enhanced, while some new physical mechanisms and phenomena emerge simultaneously, which would significantly complicate the numerical simulation of MSRs. The dual roles of molten fuel salt in the core lead to a tighter coupling of physical mechanisms since the released fission energy will be absorbed immediately by the molten salt itself and then transferred to the primary heat exchanger. The modeling of multi-physics coupling is regarded as one important aspect of MSR study, attracting growing attention worldwide. Up to now, great efforts have been made in the development of MSR multi-physics coupling models over the past 60 years, especially after 2000, when MSR was selected for one of the GEN-IV advanced reactors. In this paper, the development status of the MSR multi-physics coupling model is extensively reviewed in the light of coupling models of N-TH (neutronics and thermal hydraulics), N-TH-BN (neutronics, thermal hydraulics, and burnup) and N-TH-BN-G (neutronics, thermal hydraulics, burnup, and graphite deformation). The problems, challenges, and development trends are outlined to provide a basis for the future development of MSR multi-physics coupling models.

Funder

National Natural Science Foundation of China

Natural Science Foundation of Shanghai, China

Chinese TMSR Strategic Pioneer Science and Technology Project

Publisher

MDPI AG

Subject

Energy (miscellaneous),Energy Engineering and Power Technology,Renewable Energy, Sustainability and the Environment,Electrical and Electronic Engineering,Control and Optimization,Engineering (miscellaneous),Building and Construction

Reference108 articles.

1. Transition to thorium fuel cycle on a heavy water moderated molten salt reactor by using low enrichment uranium;Wu;Ann. Nucl. Energy,2022

2. Perspectives of the thorium fuel cycle;Lung;Nucl. Eng. Des.,1998

3. Technology Roadmap for Generation IV Nuclear Energy Systems; GIF Technical Report No. GIF-002-00; GIF: 2002. 2022.

4. Haubenreich, P.N., Engel, J.R., Prince, B.E., and Claiborne, H.C. Technical Report No. ORNL-TM-730. MSRE Design and operations Report; Part III. Nuclear Analysis, 1964.

5. Dolan, T.J. Molten Salt Reactors and Thorium Energy, 2017.

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