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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Nuclear Science and Engineering
December 2024
Nuclear Technology
Fusion Science and Technology
November 2024
Latest News
Siting of Canadian repository gets support of tribal nation
Canada’s Nuclear Waste Management Organization (NWMO) announced that Wabigoon Lake Ojibway Nation has indicated its willingness to support moving forward to the next phase of the site selection process to host a deep geological repository for Canada’s spent nuclear fuel.
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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