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Division Spotlight
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.
Meeting Spotlight
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis 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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Jun 2023
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Nuclear Science and Engineering
June 2023
Nuclear Technology
Fusion Science and Technology
July 2023
Latest News
The Civil Nuclear Credit Program: An overview
Officially established on November 15, 2021, with the signing of the $1.2 trillion Infrastructure Investment and Jobs Act—aka the Bipartisan Infrastructure Law, or BIL—the Department of Energy’s Civil Nuclear Credit Program was designed to give owners/operators of commercial U.S. reactors the opportunity to apply for certification and competitively bid on credits to help support the continued operation of economically troubled units. Finally, the federal government, and not just certain farsighted state governments, would recognize nuclear energy for its important grid reliability and decarbonization attributes.
Technical Session|Panel
Friday, November 12, 2021|10:10AM–12:10PM EST
Session Chair:
Richard S. Denning
Session Organizer:
Alternate Chair:
Jeff Gabor (Jensen Hughes)
Session Producer:
Chase Blaeser
Panelists will describe recent advances in computer codes for use in Level II/III PRA with emphasis on non light water reactors. Jennifer Leute will describe improvements in the MACCS code related to radionuclide dispersion and consequence analysis. Larry Humphries will describe modifications to MELCOR to expand its applicability to advanced reactor accident behavior. Dave Grabaskas will describe advanced reactor accident modeling developments in the DOE NEAMS program. Francis Bolger will describe EPRI accident modeling development activities.
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