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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.
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
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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Matthew Denman: On Probabilistic Risk Assessment
Probabilistic risk assessment is a systematic methodology for evaluating risks associated with a complex engineered technology such as nuclear energy. PRA risk is defined in terms of possible detrimental outcomes of an activity or action, and as such, risk is characterized by three quantities: what can go wrong, the likelihood of the problem, and the resulting consequences of the problem.
Matthew Denman is principal engineer for reliability engineering at Kairos Power and the chair of the American Nuclear Society and American Society of Mechanical Engineers Joint Committee on Nuclear Risk Management’s Subcommittee of Standards Development. As a college student at the University of Florida, Denman took a course on PRA but didn’t enjoy it, because he did not see its connection to the nuclear power industry. Later, during his Ph.D. study at the Massachusetts Institute of Technology, his advisor was Neil Todreas, a well-known thermal hydraulics expert. Todreas was working on a project with George Apostolakis, who would leave MIT to become a commissioner of the Nuclear Regulatory Commission. The project, “Risk Informing the Design of the Sodium-Cooled Fast Reactor,” was a multi-university effort funded through a Department of Energy Nuclear Energy Research Initiative (NERI) grant. Todreas and Apostolakis were joined in this project by a who’s who of nuclear academia, including Andy Kadak (MIT, ANS past president [1999–2000]), Mike Driscoll (MIT), Mike Golay (MIT), Mike Lineberry (Idaho State University, former ANS treasurer), Rich Denning (Ohio State University), and Tunc Aldemir (Ohio State University).
October 1, 2021|12:00–1:30PM (1:00–2:30PM EDT)
ANS Members Only
Nuclear reactor thermal hydraulics refers to the study of fluid flow, heat and mass transfer applied to nuclear technologies. It is a discipline of fundamental importance in both design and safety analysis of nuclear reactors. The Thermal Hydraulic Division of ANS seeks to establish, stimulate, and maintain quality technical and professional approaches in all areas of nuclear thermal hydraulics. To this end, THD hosts a vibrant program that includes the largest international conference in the field (the NURETH conference series).
Research in thermal hydraulics in the United States is highly multi-disciplinary. Researchers apply advanced computational and experimental techniques to study complex phenomena In reactor systems and answer fundamental questions on flow and heat transfer physics. This research is of increasing importance as the nation seeks to develop and deploy advanced reactors, as these designs typically have several thermal hydraulics challenges.
In this webinar, we will give a select overview of thermal hydraulic research in the United States and the role THD has in promoting the exchange of ideas and recognizing excellence in the field.