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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
W. Kramer, K. Schleisiek, L. Schmidt, G. Vanmassenhove, A. Verwimp
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 281-288
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32328
Articles are hosted by Taylor and Francis Online.
The fuel element behavior under local off-normal cooling conditions and the possible pin-to-pin failure propagation are of special interest in the safety analysis of liquid-metal fast breeder reactors. In a program called Mol 7C, Kernforschungszentrum Karlsruhe and the Centre d’Etude de l’Energie Nucléaire/Studiecentrum voor Kernenergie at Mol are performing related experiments in a sodium loop in the BR2 reactor. The test section contains a 37-pin bundle of UO2 fuel with an artificial local blockage involving the 6 inner pins and parts of the pins of the second row (30 rods are active fuel pins, and 7 are stainless-steel dummy pins). After a pre-irradiation of some days, the transient test phase is initiated by interrupting the cooling in the local blockage region. The first and second of three planned experiments demonstrate that the cooling of the whole fuel bundle was not jeopardized, although several pins have failed. The performance of the third experiment had to be postponed for the end of 1979 due to the exchange of the beryllium matrix of the BR2 reactor during 1979.