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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.
Technical Session|Sponsored by THD
Wednesday, November 15, 2023|3:15–5:00PM EST|Columbia 10
Session Chairs:
Subash L. Sharma (UML)
Tri Nguyen (Penn State)
Session Organizer:
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Modeling of Prismatic High Temperature Reactors in Pronghorn
3:15–3:35PM EST
Vasileios Kyriakopoulos (INL), Mauricio Tano (INL), Sebastian Schunert (INL)
Paper
Simulation of a Postulated Severe Assembly Blockage Accident in a Sodium Fast Reactor with the SAS4A/SASSYS-1 Safety Analysis Code
3:35–3:55PM EST
Adrian Tentner (ANL), Taeil Kim (ANL)
CFD Study of Two-Phase Flow in Helical Tube Steam Generator
3:55–4:15PM EST
Doh Hyeon Kim (KAIST), Seunghwan Oh (KAIST), Jeong Ik Lee (KAIST)
Simulations of Online Refueling Transients in a Generic Stable Salt Reactor
4:15–4:35PM EST
Thanh Hua (ANL), Yan Cao (ANL), Luke Godfrey (Moltex Energy), Tom Taylor (Moltex Energy)
Influence of Containment Design Parameters on Analysis of Depressurized Loss of Forced Cooling of Gas-Cooled Fast Modular Reactor Using MELCOR Code
4:35–4:55PM EST
WooHyun Jung (Univ. Wisconsin, Madison), SeungKyo Jung (Univ. Wisconsin, Madison), Cole Dunbar (Univ. Wisconsin, Madison), Michael Corradini (Univ. Wisconsin, Madison)
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