Development of Two-Step Method for Fast Chloride MSR Neutronics

Lawson, Kyra; Brown, Nicholas R.

doi:10.1080/00295450.2024.2310911

Development of Two-Step Method for Fast Chloride MSR Neutronics

Journal Article · Thu Mar 21 00:00:00 EDT 2024 · Nuclear Technology

DOI:https://doi.org/10.1080/00295450.2024.2310911· OSTI ID:2337692

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University of Tennessee, Knoxville, TN (United States); University of Tennessee
University of Tennessee, Knoxville, TN (United States)

This work presents neutronics models of a small and large fast-spectrum molten chloride-salt reactor. The models are similar to designs being pursued by industry, and they may serve as generic preconceptual and simplified neutronics models that provide information for decision making in licensing-related areas. Here, the two models were created using Serpent, a Monte Carlo neutron transport code, and Moltres, a neutron diffusion core simulator tool. Specifically, this study focused on exploring the applicability of diffusion theory to fast molten salt reactor (MSR) models, the capabilities of an open-source, MSR-oriented simulation tool (Moltres), and optimal energy-group structures.

View Accepted Manuscript (DOE)

Research Organization:: University of Tennessee, Knoxville, TN (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP)

Grant/Contract Number:: AC07-05ID14517; NE0009214

OSTI ID:: 2337692

Journal Information:: Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 11 Vol. 210; ISSN 0029-5450

Publisher:: Taylor & FrancisCopyright Statement

Country of Publication:: United States

Language:: English

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