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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
NRC could improve decommissioning trust fund oversight, OIG reports
The Nuclear Regulatory Commission could do more to improve its oversight of decommissioning trust funds, according to an assessment by the NRC’s Office of Inspector General. In particular, the assessment, which was conducted by Crowe LLP on behalf of the OIG, identified four areas related to developing policies and procedures, workflows, and other support that would enhance NRC oversight of the trust funds.
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.