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DOE OSTI · 2467506

SAM Code Improvements for Molten Salt Reactor Transient and Species Transport Modeling

Mui, Travis·O'Grady, Daniel J.·Zou, Ling·Hu, Rui·Salko, Robert K.
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Abstract

The SAM code is under development and supported by DOE-NE’s Nuclear Energy Advanced Modeling and Simulation program as a modern system-level modeling and simulation tool for advanced non-light water reactor safety analyses. These advanced reactor concepts incorporate novel and improved approaches to achieve safety and economic feasibility. This report summarizes FY24 efforts in addressing the modeling gaps in SAM for molten salt reactor (MSR) applications. These efforts focused on the solver performance related to species transport, usability of the flowing decay heat and delayed neutron precursor capabilities, and modeling gaps related to fission product transport throughout the system.

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Mui, Travis, O'Grady, Daniel J., Zou, Ling, Hu, Rui, Salko, Robert K.. 2024-09-01. SAM Code Improvements for Molten Salt Reactor Transient and Species Transport Modeling. https://doi.org/10.2172/2467506

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