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

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

doi:10.1080/00295450.2024.2409601

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

Journal Article · Thu Oct 17 00:00:00 EDT 2024 · Nuclear Technology

DOI:https://doi.org/10.1080/00295450.2024.2409601· OSTI ID:2474724

^[1]; ^[1]; O’Grady, Daniel ^[1]; Mui, Travis ^[1]; Ooi, Zhiee Jhia ^[1]; Hu, Guojun ^[1]; Cervi, Eric ^[1]; Yang, Gang ^[1]; Andrs, David ^[2]; ^[2]; Permann, Cody ^[1]; ^[3]; Zhou, Quan ^[4]; Fick, Lambert ^[4]; Heald, Alexander ^[4]; Zhao, Haihua ^[4]

Argonne National Laboratory (ANL), Argonne, IL (United States)
Idaho National Laboratory (INL), Idaho Falls, ID (United States)
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Kairos Power LLC, Alameda, CA (United States)

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. Finally, 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.

View Accepted Manuscript (DOE)

Research Organization:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Argonne National Laboratory (ANL), Argonne, IL (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Organization:: USDOE Office of Nuclear Energy (NE), Nuclear Energy Advanced Modeling and Simulation (NEAMS); USDOE Laboratory Directed Research and Development (LDRD) Program

Grant/Contract Number:: AC07-05ID14517; AC02-06CH11357; AC05-00OR22725

OSTI ID:: 2474724

Alternate ID(s):: OSTI ID: 2499801

Journal Information:: Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 9 Vol. 211; ISSN 0029-5450

Publisher:: Taylor & FrancisCopyright Statement

Country of Publication:: United States

Language:: English

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