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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
Standards Program
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June 2025
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Beyond conventional boundaries: Innovative construction technologies pave the way for advanced reactor deployment
In a bid to tackle the primary obstacle in nuclear deployment—construction costs—those in industry and government are moving away from traditional methods and embracing innovative construction technologies.
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)
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