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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.
Roger H. Cook
Nuclear Technology | Volume 66 | Number 2 | August 1984 | Pages 283-288
C.2. Creep Property | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33431
Articles are hosted by Taylor and Francis Online.
Creep and structural data are presented on three casts of Inconel alloy 617 tested in air and controlled impurity helium for times up to 42 000 h in a test facility at CIIR, Oslo. Prior cold work reduced initial creep rate at 850°C, but it also reduced the room-temperature tensile ductility measured after samples had been subjected to small creep strains. The main effect of environment was that air promoted high rupture ductilities, relative to the helium atmosphere used in this work. It was found that air testing caused nucleation and growth of many oxidefilled cracks. Carburization occurred during the helium tests, but this had little influence on rupture life (relative to air tests) under the experimental conditions used here. Structural examination showed that creep conditions favored the precipitation of carbides on grain boundaries transverse to the imposed tensile stress.