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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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Education and training to support Canadian nuclear workforce development
Along with several other nations, Canada has committed to net-zero emissions by 2050. Part of this plan is tripling nuclear generating capacity. As of 2025, the country has four operating nuclear generating stations with a total of 17 reactors, 16 of which are in the province of Ontario. The Independent Electricity System Operator has recommended that an additional 17,800 MWe of nuclear power be added to Ontario’s grid.
Robert P. Martin
Nuclear Technology | Volume 211 | Number 12 | December 2025 | Pages 2889-2902
Review Article | doi.org/10.1080/00295450.2024.2431778
Articles are hosted by Taylor and Francis Online.
The U.S. Nuclear Regulatory Commission (NRC) is actively updating its regulatory framework with industry stakeholder input under a program called the Licensing Modernization Project (LMP). Improvements are expected to better align the reactor licensing process with the needs of advanced reactor technologies by adopting technology-inclusive language, reducing prescriptive rules, and expanding the role of risk-informed and performance-based issue resolution.
This paper presents a technology-inclusive evaluation model that integrates both risk-based and deterministic features, drawing on data from historical licensing practices, U.S. and international safety standards, and industry case studies. The safety case content of a risked-informed safety analysis report (SAR), such as one consistent with the LMP model in the United States, is expected to logically connect risk insights with the resolution of safety and technical issues. While a mix of deterministic safety and quantitative risk-based evaluation models is explicitly addressed in the NRC’s draft rule [Code of Federal Regulations, Title 10, “Energy,” Part 53, “Risk Informed, Technology-Inclusive Regulatory Framework for Advanced Reactors” (10 CFR 53)], this paper identifies preferred applications for best-estimate plus uncertainty evaluation models in risk-informed SARs for safety margin management, supporting streamlined regulatory review for advanced reactor technologies.