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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Powering the future: How the DOE is fueling nuclear fuel cycle research and development
As global interest in nuclear energy surges, the United States must remain at the forefront of research and development to ensure national energy security, advance nuclear technologies, and promote international cooperation on safety and nonproliferation. A crucial step in achieving this is analyzing how funding and resources are allocated to better understand how to direct future research and development. The Department of Energy has spearheaded this effort by funding hundreds of research projects across the country through the Nuclear Energy University Program (NEUP). This initiative has empowered dozens of universities to collaborate toward a nuclear-friendly future.
Masao Kitamura, Eishi Ibe, Shunsuke Uchida, Takashi Honda, Glauco Romeo, Robert L. Cowan
Nuclear Science and Engineering | Volume 89 | Number 1 | January 1985 | Pages 61-69
Technical Paper | doi.org/10.13182/NSE85-A17883
Articles are hosted by Taylor and Francis Online.
60Co accumulation on boiling water reactor (BWR) primary cooling pipings. To demonstrate the treatment effect, test specimens, which had been exposed to simulated BWR water in an autoclave (temperature, 286 °C; pH, 7; oxygen concentration, 200 ppb) for up to 200 h, were installed in the Hatch-2 inplant loop and their 60Co deposition amounts were compared with those of as-received specimens. Preoxidation treatment for 200 h resulted in deposits of about one-fourth those of as-received specimens. It was estimated that the maximum amount of 60Co deposited on primary piping during the entire plant operation life (30 yr) would be reduced to about one-half of that without preoxidation treatment if the 60Co concentration in the reactor water was constant.