Initial calculations for source term of Molten Salt Reactors

This paper provides an overview of the current MSR design space and lists unique features of the various designs under consideration. Some general considerations for source terms calculation for Molten Salt Reactors (MSRs) are explained. Applicability and limitations of terminology currently defined...

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Bibliographic Details
Published in:Progress in nuclear energy (New series) 2021-02, Vol.132 (C), p.103616, Article 103616
Main Authors: Wheeler, Alexander M., Singh, Vikram, Miller, Laurence F., Chvála, Ondřej
Format: Article
Language:English
Subjects:
Actinides
Bubbling
Fission products
Fuel cycles
LFTR
Light water reactors
Mathematical analysis
MCFR
Molten salt burnup calculations
Molten salt nuclear reactors
MSR
MSR accident scenarios
Nuclear fission
Nuclear fuels
Nuclear reactors
Reprocessing
Salt
Source release
Source term
Terminology
Thorium
Uranium
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Summary:This paper provides an overview of the current MSR design space and lists unique features of the various designs under consideration. Some general considerations for source terms calculation for Molten Salt Reactors (MSRs) are explained. Applicability and limitations of terminology currently defined for legacy light water reactor (LWR) systems are discussed in the view of MSRs and the need for updated terminology is discussed. Calculations carried out for the Molten Salt Reactor Experiment (MSRE) are discussed with a qualitative comparison to the designs presented. The nature of the fission products (FPs) and actinides for Low enriched uranium, thorium and fast U/Pu fuel cycles employed in representative molten salt reactor systems are discussed. Computational results are obtained from a code (Serpent 2) with online reprocessing. Divergence in source terms when fission product bubbling is demonstrated. The source release for each molten salt reactor during postulated accidents is also presented. [Display omitted] •Discussion on terminology for molten salt source terms and accident scenarios are presented.•Burnup calculations and assumptions for source term analysis is presented.•Three molten salt reactor designs are compared against each other with respect to source term release.
ISSN:0149-1970
1878-4224
DOI:10.1016/j.pnucene.2020.103616