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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.
R. Förthmann
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 81-92
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32882
Articles are hosted by Taylor and Francis Online.
Four irradiation experiments for testing the efficiency of fission-product-retaining kernel additives in coated fuel particles are described. The evaluation of the obtained experimental data led to the following results: 1. Alumina-silica kernel additives reduce the inpile release of 90Sr and 140Ba from BISO-coated particles at temperatures of ∼1200°C by two orders of magnitude, and the cesium release from kernels by about one order of magnitude. 2. Effective transport coefficients including all parameters that contribute to kernel release for (Th,U)O2 mixed oxide kernels and low-enriched UO2 kernels containing 5 wt% alumina-silica additives are given by the equations: and 3. Alumina-silica kernel additives are ineffective for retaining 110m Ag in coated particles. However, an intact silicon carbide interlayer was also found to be ineffective at temperatures >1200°C. 4. The penetration of fission-product-containing eutectic additive melts into the buffer layer during irradiation can be avoided by using additives that consist of alumina and mullite without an excess of silica. 5. Annealing of LASER-failed irradiated particles and results of the irradiation test FRJ2-P20 indicate that the efficiency of alumina-silica kernel additives is not altered if the coating becomes defective.