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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.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
Robert C. Doerner, Theodore H. Bauer,Charles L. Fink, William F. Murphy, Arthur E. Wright
Nuclear Technology | Volume 58 | Number 3 | September 1982 | Pages 465-482
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32981
Articles are hosted by Taylor and Francis Online.
Received September 28, 1981 Accepted for Publication February 26, 1982 Issues related to the potential for a large-scale sodium vapor explosion in a carbide-fueled liquid-metal fast breeder reactor accident were addressed in the AX1 test in the Transient Reactor Test Facility. Test design and operating conditions were selected to meet the spontaneous nucleation temperature criterion for an energetic, explosive molten fuel-sodium interaction. Although that criterion appears to have been achieved, thermal and mechanical analyses of the test data indicate that the interaction was not especially energetic. Comparison to similar tests on oxide fuel indicates that, under the particular test conditions employed, the conversion of thermal energy to mechanical work is similar for the two fuel types. Transient bulk fuel motion was extensive, with axial fuel motion generally coinciding in time and space with the ejection of the coolant from the original fuel region. Posttest examination of the hardware revealed that nearly all of the fuel had mixed on a microscopic scale with the stainless steel cladding. Relative proportions of iron, chromium, and nickel in the mixture varied widely. The melting point of the mixture was apparently much lower than that of stainless steel.