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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
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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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.
Rikizo Watanabe
Nuclear Technology | Volume 66 | Number 1 | July 1984 | Pages 69-74
A. Selection, Production, and Development of Alloys for HTGR Component | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33456
Articles are hosted by Taylor and Francis Online.
A grain boundary precipitation treatment was studied for the purpose of improving the high-temper-ature low-cycle fatigue strength of a Ni-23% Cr- 18% W alloy, SSS113M, which had been developed as an intermediate heat exchanger material of very high temperature reactors and evaluated as the best alloy in the national R&D program of nuclear steelmaking in Japan. A conventional standard solution treatment of 1300°C × 1 h water quenched does not cause any grain boundary precipitation in SSS113M, but an additional heat treatment of 1250°C × 1 h causes discontinuous grain boundary precipitation of the alpha-tungsten phase. This grain boundary precipitation treatment results in two- to fivefold increases of low-cycle fatigue lives at 800°C as well as slight increases of the creep and stress rupture strength at 1000°C.