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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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.
Woo Sik Jung, Nam Zin Cho
Nuclear Science and Engineering | Volume 108 | Number 4 | August 1991 | Pages 384-395
Technical Paper | doi.org/10.13182/NSE91-A23836
Articles are hosted by Taylor and Francis Online.
Based on the maximum entropy principle used to reconstruct the neutron flux distribution in nodal calculations, an improved method that utilizes Lagrange multipliers and incorporates corner-point fluxes is described. The probability distribution that maximizes the entropy provides the most unbiased objective probability distribution within the partial information known. The flux distribution on the boundary of a fuel assembly is transformed into the probability distribution in the entropy expression. The most objective boundary flux distribution is then deduced by numerical evaluation of the Lagrange multipliers. This boundary flux distribution is used as the boundary condition in an embedded heterogeneous assembly calculation to provide the detailed flux distribution.