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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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February 2025
Latest News
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.
Hubertus Nickel, Philip J. Ennis, Florian Schubert, Hans Schuster
Nuclear Technology | Volume 58 | Number 1 | July 1982 | Pages 90-106
Technical Paper | Material | doi.org/10.13182/NT82-A32962
Articles are hosted by Taylor and Francis Online.
As in conventional high temperature technology, the qualification of metallic materials for high temperature reactor (HTR) applications is based on creep behavior, fatigue properties, corrosion resistance, and thermal stability. Of specific interest are the effects of the primary coolant helium, which contains trace impurities of hydrogen, methane, carbon monoxide, and water vapor, on mechanical behavior. In addition, irradiation effects on the properties of absorber rod cladding and tritium permeation from the primary coolant into the process gas are important areas for investigation. The results show that, for test times of up to 20 000 h, the creep-rupture strength in air and in HTR helium lies in the same scatter band. The results of low cycle fatigue tests indicate a beneficial effect of HTR helium on the cycles of failure. Investigations of corrosion in HTR helium have shown that acceptable corrosion resistance can be achieved by strict control of the impurity content of the helium. Using the available creep-rupture data and the linear damage accumulation rule, the acceptable service lives of intermediate heat exchanger tubes were calculated for Inconel alloy 617 at 950°C. The data that are being accumulated from the various test programs will form the basis of a design code for nuclear components operating at temperatures >800 °C.