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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
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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Latest News
ANS announces 2025 Presidential Citations
One of the privileges of being president of the American Nuclear Society is awarding Presidential Citations to individuals who have demonstrated outstanding effort in some manner for the benefit of ANS or the nuclear community at large. Citations are conferred twice each year, at the Annual and Winter Meetings.
ANS President Lisa Marshall has named this season’s recipients, who will receive recognition at the upcoming Annual Conference in Chicago during the Special Session on Tuesday, June 17.
Izabela Gutowska, Taylor N. Coddington, Brian G. Woods (Oregon State Univ)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 1183-1192
To support the development of the scientific and technical bases that could lead to the commercialization of the Pebble Bed High Temperature Gas Cooled Reactor, Oregon State University (OSU) is in the process of developing a conceptual Pebble Bed experimental test program. OSU designed and constructed the integral effects test (IET) facility to study Very High Temperature Gas Cooled Reactors (VHTR). The facility, called the High Temperature Test Facility (HTTF), reproduces the integral transient thermal hydraulic response under various accidents conditions of the prototype reactor design. The test data will serve as a basis for thermal hydraulic code validation. The OSU HTTF, currently configured to model a prismatic core block design, may be capable of meeting the needs for a pebble bed reactor system integral test program. In order to do that, a redesign of the facility is required. Redesign criteria should not only conform to the existing facility layout but also follow the similarity criteria and be coherent with dimensional analyses with reference to the selected prototype, pebble bed reactor model. The objective of this paper is to expand the utilization of a currently operating integral gas cooled reactor thermal fluid test facility to the validation of the design and safety thermal-hydraulic methods of the pebble bed reactor. The experiments that will be used to generate data for the NGNP thermal-fluids validation matrix will most be related to the Chinese HTR-PM reference reactor via scaling relationships. This paper summarizes test facility redesign aspects including scaling parameters, materials selection, components replacement, heating concept and instrumentation needs.