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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
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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The when, where, why, and how of RIPB design
The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) held another presentation in its monthly Community of Practice (CoP) series.
Watch the full webinar here.
Technical Session|Sponsored by FCWMD
Monday, June 8, 2020|3:30–5:15PM EDT
Session Chair:
Christina Leggett (DOE)
Alternate Chair:
Stephanie H. Bruffey
Staff Producer:
Daniel Goldberg (American Nuclear Society)
The need for extended dry and wet storage and potential transportation of commercial spent nuclear fuel (SNF) is of heightened interest to various stakeholders. In this paper session, speakers will present recent studies and activities associated with the safe storage and transportation (e.g., advances in, demonstrations of, studies of, etc. cask/overpack system designs or site infrastructure improvements) of commercial SNF.
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Analysis of Potential Standardized Canister Deployments at Commercial US Nuclear Reactor Sites
Robby Joseph (ORNL), Riley Cumberland (ORNL), Rob Howard (ORNL)
Paper
Rapid Analytic Determination of Dry Cask Storage Canister Internal Temperatures
Evan T. Palmer (Univ. of Pittsburgh), Matthew M. Barry (Univ. of Pittsburgh)
Development of a CFD Model for the Drying of Aluminum-clad Spent Fuel
Nathaniel Cooper (Univ. of South Carolina), Jamil Khan (INL), Tanvir Farouk (INL), Yi Wang (INL), Rebecca Smith (INL), Travis Knight (Univ. of South Carolina)
Inverse Depletion of Used Nuclear Fuel: a Bayesian Approach
Bassam A. Khuwaileh (Univ. of Sharjah), Fatima I. Al-Hamadi (Univ. of Sharjah), Mohammad A. Al-Shabi (Univ. of Sharjah), Walid A. Metwally (Univ. of Sharjah)
Presentation Video (Visible to Attendees)
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