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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
Workshop
Thursday, April 8, 2021|11:45AM–1:00PM EDT
Session Chair:
Mihai A. Diaconeasa
Alternate Chair:
Arjun Earthperson (NC State Univ.)
Session Organizer:
Edward Chen (NC State Univ.)
Track Organizer:
Session Producers:
Alp Tezbasaran (NCSU)
How safe is safe enough? Probabilistic Risk Assessment (PRA), also called Quantitative Risk Assessment (QRA), has been very effective in supporting better decisions on how to manage safety by making the risks involved, the contributors, and the options for controlling the risk transparent; and, quantifying the uncertainties, the primary contributor to rare event risk. Moreover, a new generation of methodologies, often referred to as Dynamic PRA (DPRA) or simulation-based PRA, is starting to receive attention for nuclear reactor PRA. These methodologies explicitly account for the time element in the probabilistic system evolution, quantify the effects of phenomenological variability and uncertainties, and are driven by plant analysis tools (e.g., RELAP, MAAP5) to model possible dependencies among failure events that may arise from hardware/software/human interactions. They have shown great promise in reducing user-to-user analysis variability, modeling passive safety systems, aging effects, and human performance. This workshop will cover the principles of PRA, hands-on examples, as well as brief reviews of recent developments in simulation-based PRA methodologies.
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