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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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.
David J. Dixon, Mohamed A. Elmaghrabi, Ian C. Rickard
Nuclear Technology | Volume 57 | Number 2 | May 1982 | Pages 228-233
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A26285
Articles are hosted by Taylor and Francis Online.
With the everchanging economic and licensing environment of the nuclear fuel cycle, Combustion Engineering (C-E) considered reducing the fuel pellet diameter of its current fuel rod designs. However, the economic incentive to reduce the diameter, considering the uncertainty of the assumptions used for the economics analysis, is at best very small. This together with the negative aspects of reduced safety margins, the increased number of discharge fuel assemblies that have to be stored or disposed of each year, and the change from a design of proven reliability all yield the conclusion that the current fuel pellet diameters used by C-E should not be changed. The conclusion differs from that reported by others as a result of the use of more sophisticated neutronics calculations and more realistic definition of fuel cycle cost parameters. This analysis was performed using C-E’s most advanced neutronics model, DIT. The model was applied to high burnup fuel (48 MWd/kgU) and cores operating on 18-month cycles. To maintain constant batch average discharge burnup and constant energy production, the number of assemblies in each reload batch was increased as the fuel pellet radius decreased. Finally, the fabrication and disposal price was adjusted as the assembly loading decreased such that the cost to fabricate or dispose of each assembly was kept constant.