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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. Rauck, R. Sanchez, I. Zmijarevic, M. Nobile
Nuclear Science and Engineering | Volume 135 | Number 1 | May 2000 | Pages 73-83
Technical Paper | doi.org/10.13182/NSE00-A2126
Articles are hosted by Taylor and Francis Online.
Through the introduction of appropriate boundary conditions, the use of multigroup albedos permits one to concentrate the numerical effort of solving the transport equation in only the domain of interest, thus reducing computational requirements. Multigroup albedos that are representative of an external medium can be calculated via independent transport calculations and collapsed for use in a few-group three-dimensional transport calculation. The multigroup albedo method is developed and applied to the calculation of the Orphée research reactor. Numerical comparisons between full-core two-dimensional transport calculations and two-dimensional transport calculations performed with multigroup albedos show why the method is interesting. The axial power distribution obtained from a three-dimensional transport calculation with multigroup albedos precisely matches measured experimental values, while results from three-dimensional full-core diffusion calculations give unacceptable errors.