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

Rui Hu, Ling Zou, Daniel O’Grady, Travis Mui, Zhiee Jhia Ooi, Guojun Hu, Eric Cervi, Gang Yang, David Andrs, Alex Lindsay, Cody Permann, Robert Salko, Quan Zhou, Lambert Fick, Alexander Heald, Haihua Zhao

Nuclear Technology / Volume 211 / Number 9 / September 2025 / Pages 1883-1902

Research Article / dx.doi.org/10.1080/00295450.2024.2409601

Received:May 22, 2024
Accepted:September 17, 2024
Published:August 7, 2025

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.