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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
House E&C members question the DOE
As work progresses on the Department of Energy’s Nuclear Reactor Pilot Program, which will progress through DOE authorization rather than Nuclear Regulatory Commission licensing, three members of the House Committee on Energy and Commerce have sent a critical letter to Energy Secretary Chris Wright.
The letter demands “information about the DOE and its employees’ dealings with the NRC and its staff” and expresses concern that DOE staff has “broken the firewall” between the departments.
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 | doi.org/10.1080/00295450.2024.2409601
Articles are hosted by Taylor and Francis Online.
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.