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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.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
W. R. Johnson, L. D. Thompson, Thomas A. Lechtenberg
Nuclear Technology | Volume 66 | Number 1 | July 1984 | Pages 88-101
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-A33458
Articles are hosted by Taylor and Francis Online.
The utilization of the high-temperature gas-cooled reactor (HTGR) for advanced or process heat applications will require the use of wrought components operating at temperatures up to 1000°C (1832°F) for times approaching 30 yr. Alloys for such components must withstand the corrosive effects (carburization and oxidation) of the impure helium primary coolant environment and maintain adequate elevated temperature strength. Commercially available wrought alloys have been found to be seriously limited for such applications because of their inherently poor resistance to corrosion in impure helium. As one approach to the solution of this problem, a program has been initiated to develop wrought alloys having a better combination of corrosion resistance and high-temperature strength, under advanced HTGR conditions, than commercial alloys currently available. This program culminated in 1980 with the design, melting, and fabrication of ten experimental Ni-Cr-Mo-W-Al-Ti-Zr-C alloys and with the initiation of efforts to evaluate their corrosion and mechanical behavior. Results of tests showed that all the experimental alloys exhibited superior carburization resistance in advanced reactor helium. In addition, several of the alloys exhibited excellent mechanical properties, including, in the case of one alloy, creep rupture strength at 900°C (1652°F), significantly better than that of the commercial alloy Inconel-617.