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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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.
F. Maekawa, Y. Oyama
Nuclear Science and Engineering | Volume 125 | Number 2 | February 1997 | Pages 205-217
Technical Paper | doi.org/10.13182/NSE97-A24267
Articles are hosted by Taylor and Francis Online.
Neutron spectra below 10 keV in an iron shield assembly bombarded by deuterium-tritium neutrons are measured with accuracy between 5 to 13% by adopting the slowing-down time method. The measurement supplemented previous spectrum measurements for higher energies so that the neutron spectrum in the whole energy range from 14 MeV down to 0.3 eV is now available. Benchmark tests of iron data in JENDL-3.1, JENDL-3.2, JENDL fusion file, and FENDL/E-1.0 were carried out in the whole energy range with experimental uncertainty at ∼10% by utilizing the present and previous experiments. As a result, it was found that cross-section data in the newer versions of JENDL were improved in terms of agreement with the experiment. Calculation with JENDL fusion file and FENDL/E-1.0 could predict neutron fluxes in the whole energy range within 20 and 15%, respectively. Possible over- and underestimations for nonelastic and elastic cross sections, respectively, at 14 MeV in all JENDLs were pointed out. It was confirmed that low-energy neutron fluxes were very sensitive to Q values for discrete inelastic cross sections of natural iron and 57Fe(n,n’1,) reaction, which were not adequately treated in JENDL-3.1.