SAM: A Modern System Code for Advanced Non-LWR Safety Analysis
The System Analysis Module (SAM), developed at Argonne National Laboratory and by collaborators at other organizations, is for advanced non–light water reactor safety analysis. SAM aims to provide fast-running, modest-fidelity, whole-plant transient analysis capabilities that are essential for fast-turnaround design scoping and engineering analyses of advanced reactor concepts. To facilitate code development, SAM utilizes the MOOSE object-oriented application framework, its underlying finite element library, and linear and nonlinear solvers to leverage modern advanced software environments and numerical methods. SAM aims to solve tightly coupled physical phenomena, including fission reaction, heat transfer, fluid dynamics, and thermal-mechanical responses in advanced reactor structures, systems, and components with high accuracy and efficiency. This paper gives an overview of the SAM code development, including goals and functional requirements, physical models, current capabilities, verification and validation, software quality assurance, and examples of simulations for advanced nuclear reactor applications.
Authors
- Zhiee Jhia Ooi (ORCID: https://orcid.org/0000-0003-3027-8516)
- Travis Mui (ORCID: https://orcid.org/0000-0003-0373-6470)
- Robert Salko (ORCID: https://orcid.org/0000-0002-5356-6679)
- Lambert Fick (ORCID: https://orcid.org/0000-0002-2944-1294)
- Eric Cervi (ORCID: https://orcid.org/0000-0002-2137-3645)
- Cody Permann (ORCID: https://orcid.org/0000-0001-5336-2863)
- Guojun Hu
- David Andrš (ORCID: https://orcid.org/0000-0002-8913-902X)
- Gang Yang (ORCID: https://orcid.org/0000-0001-7063-9182)
- Ling Zou (ORCID: https://orcid.org/0000-0003-0664-0474)
- Rui Hu (ORCID: https://orcid.org/0000-0002-3771-2920)
- Alexander Heald
- Haihua Zhao (ORCID: https://orcid.org/0000-0002-8794-1027)
- Quan Zhou (ORCID: https://orcid.org/0000-0002-3819-3878)
- Alex Lindsay
- Daniel O’Grady
Institutions
- Argonne National Laboratory (US)
- Oak Ridge National Laboratory (US)
- Idaho National Laboratory (US)
- Kairos (United States) (US)
- Kairos Power (United States)
Publication Details
- Journal
- Nuclear Technology
- Published
- 2024-10-17
- DOI
- https://doi.org/10.1080/00295450.2024.2409601
- Citations
- 9
- Primary Topic
- Nuclear reactor physics and engineering
- Type
- article
- Field-Weighted Citation Impact
- 11.69
Funders
- Oak Ridge National Laboratory