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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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May 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
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 RPD
Thursday, June 11, 2020|10:00–11:45AM EDT
Session Chair:
Jason Hearne (LANL)
Alternate Chair:
Pavel Tsvetkov (LANL)
Session Organizer:
Track Organizer:
Staff Producer:
Jessica Vazquez (American Nuclear Society)
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A Unified Form of Stabilized Finite Element Methods for Solving the First-order Neutron Transport Equation
Liangzhi Cao (Xi’an Jiaotong Univ.), Chao Fang (Xi’an Jiaotong Univ.), Hongchun Wu (Xi’an Jiaotong Univ.)
Paper
Relaxation of Quasi-Static Approach via Polynomial Interpolation in the Predictor Corrector Quasi-Static Method
T. Oh (KAIST), Yonghee Kim (KAIST)
Unstructured Mesh-Grid Multi-Physics Analysis with Monte Carlo iMC Code for Advanced Fuel Elements
Hyeontae Kim (KAIST), Yonghee Kim (KAIST)
Conceptual Safety Design Report for the Versatile Test Reactor
Doug Gerstner (INL), Jason Andrus (INL), Troy Reiss (INL)
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