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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.
Francis H. Lewis, Patrick D. Soran
Nuclear Science and Engineering | Volume 68 | Number 1 | October 1978 | Pages 116-125
Technical Note | doi.org/10.13182/NSE78-A27277
Articles are hosted by Taylor and Francis Online.
Monte Carlo neutron transport calculations of critical radii of bare UH3 spheres as a function of 233U and 235U enrichment in 238U were carried out using three different calculational methods: 1. the continuous-energy 2. method the multigroup approximation 3. the probability table method. Also calculated were the average neutron removal lifetimes and median fission-producing neutron energies for these critical systems. Results of these calculations were analyzed and compared to quantify and bound self-shielding effects arising from the neutron cross-section resonances in calculating these moderated critical assemblies. Although the critical radii of these assemblies are sensitive to the resonances in 238U, the removal lifetime seems to be affected much more by the fissile isotope resonances. The probability table method gives results that are in excellent agreement with continuous-energy calculations, thereby eliminating the need for special cross-section processing for each separate enrichment when using multigroup cross sections.