Fuel depletion study of the molten salt demonstration reactor

•MSR/PWR modeled in SCALE to compare radionuclide concentration vs time and burnup.•MST based on physical transport properties of the reactor fuel materials.•SCALE packages TRITON and ORIGEN model source term generation.•Compared radionuclide generation from 5 years of PWR to 15 years of MSR operati...

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Bibliographic Details
Published in:Nuclear engineering and design 2024-03, Vol.418 (C), p.112881, Article 112881
Main Authors: Creasman, Sarah Elizabeth, Jay Harrison, T., Heilbronn, Lawrence H.
Format: Article
Language:English
Subjects:
ChemTriton
Liquid fuel
Mechanistic source term
Molten salt reactor
Nuclear Regulatory Commission
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Summary:•MSR/PWR modeled in SCALE to compare radionuclide concentration vs time and burnup.•MST based on physical transport properties of the reactor fuel materials.•SCALE packages TRITON and ORIGEN model source term generation.•Compared radionuclide generation from 5 years of PWR to 15 years of MSR operation.•MSR source term radionuclide masses less than 20% of PWR masses. In this study, a molten salt reactor model and a pressurized water reactor model were run in SCALE for comparison. The parameters of interest in the analysis were the concentrations of different nuclides in a molten salt reactor, specifically compared with concentrations of these same nuclides in a pressurized water reactor. This paper discusses this analysis, as well as discussing and comparing the burnup in both models. The results suggest that using a mechanistic source term for radionuclides instead of a bounding, conservative source term enables more realistic reactor modeling, making it a great option for licensing both advanced reactors and light-water reactors.
ISSN:0029-5493
1872-759X
DOI:10.1016/j.nucengdes.2023.112881