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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.
Bryce L. Shriver, Thomas G. Hook
Nuclear Technology | Volume 61 | Number 1 | April 1983 | Pages 113-117
Technical Paper | Material | doi.org/10.13182/NT83-A33148
Articles are hosted by Taylor and Francis Online.
The operation of some early-generation light water reactors may be limited by the irradiation-induced embrittlement of their reactor vessels. Additional nondestructive methods of measuring the actual embrittlement are desirable to support limits placed on the operation of these vessels. Previous studies have indicated that the increase in microhardness with irradiation may correlate with shifts in the ductile-to-brittle transition temperature. However, the previous research did not consider variations in the test temperature to determine whether it affects the correlation with transition temperature or whether microhardness may correlate with the fracture energy outside the transition region. The Vickers microhardness measurements were made at eight temperatures from -195 to 90°C (-320 to 200°F) by holding the samples in a liquid bath during the application of the test load. Both unirradiated and irradiated samples were evaluated for the three A533-B steels. These tests indicate that the Vickers hardness may correlate with the strength and ductility of unirradiated steels. In addition, both the change in microhardness and the shift in test temperature at a constant hardness may correlate with the shift in transition temperature caused by irradiation.
