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.

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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

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SAM: A Modern System Code for Advanced Non-LWR Safety Analysis

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9 citations
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SAM: A Modern System Code for Advanced Non-LWR Safety Analysis

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article en
9 citations

Abstract

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.

Nuclear TechnologyVol. 211(9)
Argonne National Laboratory (US), Oak Ridge National Laboratory (US), Idaho National Laboratory (US), Kairos (United States) (US), Kairos Power (United States)
Oak Ridge National Laboratory
Openalex Percentile: Top 2%
Nuclear reactor physics and engineering
11.69
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