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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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!
Latest Magazine Issues
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Deep Isolation validates its disposal canister for TRISO spent fuel
Nuclear waste disposal technology company Deep Isolation announced it has successfully completed Project PUCK, a government-funded initiative to demonstrate the feasibility and potential commercial readiness of its Universal Canister System (UCS) to manage TRISO spent nuclear fuel.
2024 International Congress on Advances in Nuclear Power Plants (ICAPP)
Technical Session|Thermal Hydraulics Analysis and Testing
Wednesday, June 19, 2024|3:15–5:00PM PDT|Palm H
Session Chair:
Dave Grabaskas (ANL)
Alternate Chair:
Rachel Thomas (ANL)
Session Organizers:
Hiroyuki Yoshida (Japan Atomic Energy Agency)
Mauricio E. Tano (INL)
Caleb S. Brooks (Univ. Illinois, Urbana-Champaign)
Track Organizers:
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Assessment of SAS4A/SASSYS-1 Using the NACIE-UP Experimental Facility
3:15–3:35PM PDT
Daniel J. O'Grady (ANL), Jun Liao (Westinghouse Electric Co.), Sung Jin Lee (Fauske & Assoc.), Rachel Thomas (ANL)
Paper
Development of One-Dimensional Freezing Model in SAM for Salt-Cooled Reactor Analysis Applications
3:35–3:55PM PDT
Ling Zou (ANL), Quan Zhou (Kairos Power), Dan O’Grady (ANL), Rui Hu (ANL), Alex Heald (Kairos Power), Haihua Zhao (Kairos Power)
MELCOR Analysis of Accident Mitigation Capability of Flooding Safety System in Korean i-SMR Under Hypothetical Loss of Coolant Accident
3:55–4:15PM PDT
Chang Hyun Song (Hanyang Univ.), JinHo Song (Hanyang Univ.), Sung Joong Kim (Hanyang Univ.)
BWR-Type SMR with Load-Following Function, FCVS, and Seismic Isolation Device that Eliminates Location Requirements
4:15–4:35PM PDT
Tadashi Narabayashi (Tokyo Institute of Technology), Hiroshige Kikura (Tokyo Institute of Technology), Kazuhiko Kasai (Tokyo Institute of Technology), Koji Endo (Rasa Industries)
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