ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
Fusion Science and Technology
Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Prodyot Roy, C. N. Spalaris
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 259-269
Technical Paper | Materials | doi.org/10.13182/NT55-259
Articles are hosted by Taylor and Francis Online.
A development program was undertaken to support the materials selection for steam generator piping and intermediate heat exchangers that are to be used in liquid-metal fast breeder reactors. Four major topics have been reviewed, and the results obtained as well as the direction of future tests have been described. These topics are carbon transport in sodium, the effect of carbon loss/gain on materials in the reactor intermediate heat transport system (IHTS), corrosion fatigue, and aqueous corrosion. Thus far, the results on hand support the initial assumptions made in specifying the use of Cr—1 Mo as the construction material for the evaporator and superheater and Type 316 piping of the IHTS. The future direction of the experimental programs is to verify further the materials choice and also to obtain information that will be essential during the plant installation and operation and the reliability of the components.