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

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

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 shi...

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Bibliographic Details
Main Authors:	Liang Chen, Liaoyuan He, Shaopeng Xia, Minyu Peng, Guifeng Zhu, Rui Yan, Yang Zou, Hongjie Xu
Format:	Article
Language:	English
Published:	MDPI AG 2024-10-01
Series:	Energies
Subjects:	molten salt reactor fission products migration species transport
Online Access:	https://www.mdpi.com/1996-1073/17/21/5448
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