ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
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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DOE-NE opens HALEU Consortium with focus on information exchange
The Department of Energy’s Office of Nuclear Energy announced December 7 that its new HALEU Consortium is open for membership. And not just from U.S. enrichers, fuel fabricators, and others working in the front-end fuel cycle, but from “any U.S. entity, association, and government organization involved in the nuclear fuel cycle,” and—at the DOE’s discretion—“organizations whose facilities are in ally or partner nations.” The HALEU Consortium will essentially serve as an information clearinghouse to meet DOE-NE’s ongoing needs for firm supply and demand data as it supports the development of a commercial domestic high-assay low-enriched uranium (HALEU) infrastructure to fuel advanced reactors. The consortium is open for business almost one full year after the DOE first requested public input on its structure.
Technical Session|Sponsored by RPD
Wednesday, November 16, 2022|3:15–5:00PM MST|Sonoran 7
Friederike Bostelmann (ORNL)
Pavel V. Tsvetkov
Massimiliano Fratoni (UC Berkeley)
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JOYO Benchmark Evaluation of the Advanced Reactor Modeling Interface
Michael Huang (TerraPower), Barry Mingst (TerraPower), Zhiwen Xu (TerraPower)
Size-Dependent Neutronic Optimization of Ultra-Long-Life Molten Salt and Metal Reactors (MSMR)
Eunhyug Lee (KAIST), Taesuk Oh (KAIST), Seongdong Jang (KAERI), Yonghee Kim (KAIST)
A Study on Control Algorithm for Daily Load-Follow Operation in the APR1400 Reactor
Husam Khalefih (KAIST), Yonghee Kim (KAIST)
A Method for Critical Control System Configuration Search when Using Monte Carlo Neutronics Codes
Dean Price (Univ. Michigan), Nathan Roskoff (Westinghouse Electric Co.)
Highlights of Neutronics Analyses for the Pre-Conceptual NIST Neutron Source Design
Osman S. Celikten (NIST Center for Neutron Research), Dagistan Sahin (NIST Center for Neutron Research), Abdullah G. Weiss (NIST Center for Neutron Research)
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