TY - JOUR
T1 - SAM
T2 - A Modern System Code for Advanced Non-LWR Safety Analysis
AU - Hu, Rui
AU - Zou, Ling
AU - O’Grady, Daniel
AU - Mui, Travis
AU - Ooi, Zhiee Jhia
AU - Hu, Guojun
AU - Cervi, Eric
AU - Yang, Gang
AU - Andrs, David
AU - Lindsay, Alex
AU - Permann, Cody
AU - Salko, Robert
AU - Zhou, Quan
AU - Fick, Lambert
AU - Heald, Alexander
AU - Zhao, Haihua
N1 - Publisher Copyright:
© 2024 Argonne National Laboratory.
PY - 2024
Y1 - 2024
N2 - 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.
AB - 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.
KW - advanced reactors
KW - safety analysis
KW - SAM
KW - systems code
UR - http://www.scopus.com/inward/record.url?scp=85207314815&partnerID=8YFLogxK
U2 - 10.1080/00295450.2024.2409601
DO - 10.1080/00295450.2024.2409601
M3 - Article
AN - SCOPUS:85207314815
SN - 0029-5450
JO - Nuclear Technology
JF - Nuclear Technology
ER -