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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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.
A. Alberman, G. Bley, P. Pépin, P. Soulat
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 639-646
G. Irradiation Behavior | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33485
Articles are hosted by Taylor and Francis Online.
Within the framework of the high-temperature gas-cooled reactor (HTGR) R&D agreement with GA Technologies, Inc., the Centre d’Etudes Nucléaires de Saclay investigated the transition temperature shift of the liner steel exposed to (thermal) neutrons. The steel was ferritic A537 (1.32% manganese, 0.26% copper, 0.26% silicon, 0.21% nickel, and 0.14% chromium). The specimens were irradiated in the French EL3 heavy water research reactor in an area where the neutron spectrum was comparable to that occurring in front of the HTGR core cavity liner:Φth/Φƒ ∼ 1000 . The temperature was 60 °C during the irradiations. For theoretical purposes, two irradiations were carried out at two different fluences. In addition, some specimens were cadmium plated to examine the effect of fast neutrons. Charpy impact tests were performed at Saclay with an instrumented impact device. The results show that current models overestimate the thermal neutron effect by a factor of 3.
