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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.
S. C. Mo, K. O. Ott
Nuclear Science and Engineering | Volume 96 | Number 2 | June 1987 | Pages 112-121
Technical Paper | doi.org/10.13182/NSE87-A16371
Articles are hosted by Taylor and Francis Online.
A practical methodology is developed to treat the resonance self-shielding transition near zone interfaces. Based on the narrow resonance approximation, a space- and energy-dependent selfshielding factor for a single interface system is derived from the integral transport theory. Using the Wigner rational approximation, the self-shielding factor for a fine region near a zone interface isfac-torized into a linear combination of individual homogeneous and heterogeneous self-shielding factors. The method has been implemented in a widely used cross-section processing code that is based on the Bondarenko f-factor method. The result of the analysis was applied to a fast reactor blanket mock-up to improve the calculations near a converter-blanket interface. Comparisons of the calculation with 238U capture experimental data measured in the Purdue Fast Breeder Blanket Facility are also discussed.
