A Comprehensive Approach to Molten Salt Reactor Source Term Generation and Shielding Analyses
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Authors
Carberry, Kyle
Petrovic, Bojan
Issue Date
2023-07-24
Type
Journal articles
Language
Keywords
Molten Salt reactor source terms , SCALE , variance reduction , prompt and delayed neutrons , neutron and gamma dose rate
Alternative Title
Abstract
The research presented herein outlines a comprehensive process for characterizing the major radiological source terms necessary for radiation protection and licensing activities that one would expect in a liquid-fueled molten salt reactor. This process leverages organic simulation tools in the SCALE modeling and simulation code suite to provide an “off-the-shelf” solution for shielding assessments of this reactor type. Ultimately, this source development process is applied to a representative molten salt reactor system to assess the impact of ex-core source terms on shielding in varying operating conditions. The results of the analysis determined that while the prompt core source is the major dose contributor outside the radiological shielding, specific ex-core features, such as the primary salt loop components and configuration, can have an appreciable dose impact, and thus must be accounted for.
Description
Citation
Carberry, Kyle, and Bojan Petrovic. “A Comprehensive Approach to Molten Salt Reactor Source Term Generation and Shielding Analyses.” Nuclear Technology 210, no. 3 (2024): 409–35. doi:10.1080/00295450.2023.2229181.
Publisher
Informa UK Limited
License
Journal
Volume
Issue
PubMed ID
ISSN
0029-5450
1943-7471
1943-7471