ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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
Fusion Science and Technology
Plan for AP1000 deployment in Poland gains more focus
Westinghouse Electric Company, Bechtel, and Polish utility Polskie Elektrownie Jądrowe (PEJ)—the three firms leading the effort to build Poland’s first nuclear power plant—have announced the signing of a new agreement that defines the main principles of cooperation on the project’s design and construction and confirms the implementation of its next major stage.
Technical Session|Sponsored by THD
Friday, December 3, 2021|1:00–2:45PM EST |Columbia 11
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SAM Code Validation of Natural Convection in Molten Salt
Jadyn Reis (Texas A&M Univ.), Michael Gorman (Texas A&M Univ.), Brent Hollrah (Texas A&M Univ.), Rodolfo Vaghetto (Texas A&M Univ.), Yassin Hassan (Texas A&M Univ.)
Validation Effort for the OSU HTTF PG-28 Test Using RELAP5-3D
Joshua K. Halsted (Oregon State Univ.), Izabela Gutowska (Oregon State Univ.)
Preliminary Analysis of Journal Bearings for Molten Salt Pumps
Yuqi Liu (Univ. of New Mexico), Minghui Chen (Univ. of New Mexico)
Preliminary Thermal-Hydraulic Analysis for Heat Pipe Irradiation Test in the MIT Reactor
Aaron S. Epiney (INL), David M. Carpenter (MIT), Justin Johnson (INL)
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