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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.
Hugo W. Bertini, Janice S. White
Nuclear Science and Engineering | Volume 69 | Number 1 | January 1979 | Pages 85-94
Technical Note | doi.org/10.13182/NSE79-A21289
Articles are hosted by Taylor and Francis Online.
Idealized equilibrium expansion calculations were made to determine the characteristics of UO2 vapor bubbles produced under sodium in the capacitor discharge vaporization experiments at the Oak Ridge National Laboratory. These characteristics are the quality of the vaporized UO2, it vapor density, and the bubble diameter. A parametric study was made over the range of initial and final states expected to occur in the experiments to determine the effects of losing arbitrary amounts of energy and of vaporizing arbitrary amounts of sodium. The results are sufficiently general to be of use in estimating bubble characteristics for a hypothetical core disruptive accident in a liquid metal-cooled fast breeder reactor.
