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Division Spotlight
Mathematics & Computation
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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
El Salvador: Looking to nuclear
In 2022, El Salvador’s leadership decided to expand its modest, mostly hydro- and geothermal-based electricity system, which is supported by expensive imported natural gas and diesel generation. They chose to use advanced nuclear reactors, preferably fueled by thorium-based fuels, to power their civilian efforts. The choice of thorium was made to inform the world that the reactor program was for civilian purposes only, and so they chose a fuel that was plentiful, easy to source and work with, and not a proliferation risk.
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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