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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
Brandon. Chisholm, Steven Krahn, Allen Croff, Paul Marotta (Vanderbilt Univ), Andrew Sowder (EPRI), Nicholas Smith (Southern Co.)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 513-522
Molten Salt Reactors (MSRs) are an example of an advanced reactor designs that differ substantially from the existing commercial technology. Because the safety assessment of such reactor designs will require consideration of hazards that are not present in light water reactors (LWRs), a flexible method is needed to comprehensively identify and analyze new hazards and event sequences. This work demonstrates the application of a specific Process Hazards Analysis (PHA) methodology to select auxiliary systems of the Molten Salt Reactor Experiment (MSRE) design in order to provide safety insights to the design of these subsystems, as well as produce results that can be carried forward into more quantitative risk assessment approaches. Additionally, ongoing work to develop an MSR-specific component reliability database to support quantitative risk assessment is also described.