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Division Spotlight
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.
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.
Peter Thomas Hughes, Donald C. Allen
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 661-666
H. Design Codes and Life Prediction | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33487
Articles are hosted by Taylor and Francis Online.
The major technical obstacle to construction of a 950°C commercial gas-cooled reactor is the absence of a clear basis for the structural design of the metal components. The basis of existing design rules for temperatures to 800°C has been subject to joint U.S. and Federal Republic of Germany review. The result of this review has been used to define complementary structural design programs. Three significant aspects of structural design at 950°C not directly addressed by existing codes have formed a partial basis for work in the United States. These are: design for flaws, for environmental effects, and for a clearly stated definition of reliability. The importance of these three aspects is illustrated, for example, by the fact that component materials, such as the nickel alloys, exhibit markedly reduced toughness below the operating temperature range after elevated temperature exposure. Such materials also display a susceptibility to major mechanical property changes resulting from carbon uptake or loss to the cooling gas. Also there is no satisfactory precedent from which to define design margins. A structural design program is described, some elements of which are being developed.