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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
Two updated standards on criticality safety published
The American National Standards Institute (ANSI) recently approved two new American Nuclear Society standards covering different aspects of nuclear criticality safety (NCS).
Technical Session|Sponsored by FCWMD
Tuesday, June 14, 2022|3:15–5:00PM PDT|Santa Monica
Session Chair:
Chaithanya Balumuru (Univ. Idaho)
Alternate Chair:
Christina Leggett (Booz Allen Hamilton/ARPA-E)
Session Organizer:
This session covers research on a broad range of fuel cycle-related topics, including laser enrichment of uranium, molten salt chemistry and machine learning analyses, recycling of Zircaloy cladding, and fuel cycle analyses.
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CRISLA-3G Advanced Laser Enrichment of Uranium
Jeff Eerkens (Crisla), Cristo Liebenberg (Crisla)
Paper
Structure Analysis of LiF-NaF-ZrF4 Molten Salts with Deep Learning Potentials
Rajni Chahal (Univ. Massachusetts, Lowell), Stephen T. Lam (Univ. Massachusetts, Lowell)
Recycling of Zircaloy from Spent Nuclear Fuel Rods Using Sulfur Chloride Reagents
Breanna Vestal (Univ. Tennessee, Knoxville), Craig Barnes (Univ. Tennessee, Knoxville), Guillermo (Bill) Daniel Del Cul (ORNL), Stephanie H. Bruffey (ORNL), Rodney Hunt (ORNL)
Solubility of Lanthanide Trichlorides in the Eutectic LiCl-KCl Molten Salt
Tejaswini Vaidya (Univ. Idaho), Haiyan Zhao (Univ. Idaho)
Using Fuel Cycle Simulators and Bayesian Inference in Nuclear Archaeology
Max Schalz (RWTH Aachen Univ.), Lewin Bormann (RWTH Aachen Univ.), Malte Göttsche (RWTH Aachen Univ.)
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