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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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Apr 2025
Jan 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Monday, June 13, 2022|3:15–5:00PM PDT|Redondo
Alternate Chair:
Jun Fang
Session Organizer:
W. David Pointer
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DNS Analysis of High Flux Isotope Reactor Subchannel
Emilian L. Popov (ORNL), Nicholas J. Mecham (NCSU), Igor A. Bolotnov (NCSU)
Paper
Evaluation of Irradiation-Induced Fuel Core Expansion on Safety Margins of LEU U-10Mo Fuel During LOCA and RIA for the University of Missouri Research Reactor
Guanyi Wang (ANL), Basar Ozar (ANL), Dhongik Yoon (ANL), John Stillman (ANL), Erik Wilson (ANL), Leslie Foyto (Univ. Missouri)
Physics-Based Inferencing for Characterization of Boundary Conditions on Thermal-Fluid System for Irradiation Vehicle
Haeseong Kim (MIT), Matteo Bucci (MIT), Sacit Cetiner (INL)
Preliminary Design Status of HALEU Annular Targets for Irradiation in the High Flux Isotope Reactor
Nolan Goth (ORNL), Jorge Navarro (ORNL), Eliott Fountain (ORNL), Alex Huning (ORNL), Chris Bryan (ORNL)
Big BUSTER Testing Environment in TREAT: Preliminary Thermal-Hydraulics for the Graphite Filler Assemblies
Aaron S. Epiney (INL), John D. Bess (INL), Nicolas E. Woolstenhulme (INL)
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