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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Nuclear Science and Engineering
August 2025
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July 2025
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Latest News
NextGen MURR Working Group established in Missouri
The University of Missouri’s Board of Curators has created the NextGen MURR Working Group to serve as a strategic advisory body for the development of the NextGen MURR (University of Missouri Research Reactor).
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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