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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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!
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Latest News
NC State releases feasibility study for new research and test reactor
North Carolina State University has completed a feasibility study for its planned advanced research and test reactor. The $3 million study, which was undertaken by the university at the direction of the North Carolina General Assembly, is described in the full report, includes recommendations and projected costs and timelines.
Reactor type: NC State prefers the new reactor to be of “a multipurpose advanced sodium-cooled mixed/coupled spectrum design,” according to the report. Such a design would make the reactor “the only sodium-cooled fast research and test reactor in the country.”
Technical Session|Sponsored by THD
Wednesday, June 10, 2020|4:35–6:20PM EDT
Session Chair:
Prashant Jain (ORNL)
Session Organizer:
Elia Merzari
Track Organizer:
Igor Bolotnov (NCSU)
Staff Producer:
Janice Lindegard (American Nuclear Society)
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Validation of the 1-D Thermal Stratification Model in Gallium Environment
Cihang Lu (Virginia Commonwealth Univ.), Zeyun Wu (Virginia Commonwealth Univ.), Brendan Ward (Kansas State Univ.), Hitesh Bindra (Kansas State Univ.)
Paper
Cooling Channel Optimization in Additively Manufactured Gas-Cooled Reactor Core
Justin Weinmeister, Prashant K. Jain
Multi-Scale & Multi-Physics Analysis of PWR Steam Line Break Accident
Jae Ryong Lee (KAERI), Han Young Yoon (KAERI), Ik Kyu Park (KAERI)
Sodium Fire Models for In- and Ex-vessel Safety Analysis Code SPECTRA
Mitsuhiro Aoyagi (Japan Atomic Energy Agency), Akihiro Uchibori (Japan Atomic Energy Agency), Takashi Takata (Japan Atomic Energy Agency), Hiroyuki Ohshima (Japan Atomic Energy Agency)
Code Validation for SBLOCA Test of PHWR using MARS-KS
Kyunglok Baek (Korea Institute of Nuclear Safety), Seon Oh Yu (Korea Institute of Nuclear Safety)
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