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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Juan J. Casal, Jan Krouthén, Manuel Albendea
Nuclear Technology | Volume 151 | Number 1 | July 2005 | Pages 51-59
Technical Paper | Advances in Nuclear Fuel Management - Core Physics and Fuel Management Methods, Analytical Tools, and Benchmarks | doi.org/10.13182/NT05-A3630
Articles are hosted by Taylor and Francis Online.
The introduction of the SVEA-96 Optima generation of advanced boiling water reactor fuel designs implies a further increment in complexity and heterogeneity that needs to be supported by accurate calculation tools. In order to take advantage of the improved economics offered by these modern fuel designs while simultaneously assuring safe and reliable reactor operation, both the reload design process and the online core monitoring procedures must be based on appropriate calculation methods. The modeling of transition cores involving the gradual introduction of these new fuel designs poses a severe challenge for the current core physics methods. Recognizing this, Westinghouse has engaged in a continuing process of improving its core physics calculation packages. This development program is supported by a comprehensive validation effort to demonstrate the accuracy and reliability of the improved methods as well as to identify areas requiring further development. The purpose of this paper is to summarize some of the results of this program.