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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
M. Kowaka, H. Nagano, T. Kudo, Y. Okada, M. Yagi, O. Takaba, T. Yonezawa, K. Arioka
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 394-404
Technical Paper | Materials | doi.org/10.13182/NT55-394
Articles are hosted by Taylor and Francis Online.
It was shown that a modified Huey test, i.e., a 24-h immersion in boiling 40% HNO3, is able to exactly detect the susceptibility to intergranular corrosion of Alloy 600, which is correlated with intergranular stress corrosion cracking (IGSCC) behavior in high temperature water containing small amounts of chloride ions. Chromium content at the regions adjacent to grain boundaries in sensitized Alloy 600 was analyzed as ∼3% by the measurement of magnetic susceptibility. Heat treating Alloy 600 at low temperatures, e.g., at 700°C for 15 h, improves the IGSCC resistance to both high temperature water and caustic solutions by constructing suitable micro structures resistant to sensitization, in which chromium carbides precipitate predominantly in the matrix instead of grain boundaries.