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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
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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Latest News
EnergySolutions to help explore advanced reactor development in Utah
Utah-based waste management company EnergySolutions announced that it has signed a memorandum of understating with the Intermountain Power Agency and the state of Utah to explore the development of advanced nuclear power generation at the Intermountain Power Project (IPP) site near Delta, Utah.
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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