Development and Verification of a Multi-Physics Transport Code of Molten Salt Reactor Fission Products

• Published in: Energies (Basel) 2024-11, Vol.17 (21), p.5448
• Main Authors: Chen, Liang, He, Liaoyuan, Xia, Shaopeng, Peng, Minyu, Zhu, Guifeng, Yan, Rui, Zou, Yang, Xu, Hongjie
• Format: Article
• Language: English
• Subjects: fission products migration; Fluorides; Gases; Graphite; Interfaces; molten salt reactor; Nuclear reactors; Physics; Radiation; Reynolds number; species transport
• ISSN: 1996-1073; 1996-1073
• DOI: 10.3390/en17215448

The transport of fission products in molten salt reactors has attracted much attention. However, few codes can completely describe the transport characteristic, though the migration of fission products in the molten salt reactor is essential to estimate the source term, decay heat, and radiation shielding. This study built a program named ThorFPMC (Thorium Fission Products Migration Code) that can handle the multi-physics transport characteristic based on the flow burnup code ThorMODEc (Thorium MOlten Salt Reactor Specific DEpletion Code). A problem-related depletion chain compression method was applied to decrease the order of the solve matrix. The matrix exponential and splitting methods were applied to solve the steady state and transient calculation, respectively. Error analysis showed that for a specific problem, the simplified depletion chain matrix index method could solve the fission products migration equation with an arbitrary time-step with high speed (s) and high precision (10−4); the splitting method could reach a precision of 10−2 level for the full fuel depletion chain, multi-nodes, and transient problems. Compared to the Strang splitting method, the perturbation splitting method has higher precision and less time consumption. In summary, the developed programmer could describe the migration effect of fission products in molten salt reactors, which provides a significant tool for the design of molten salt reactors.