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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.
D. J. Grady, G. F. Knoll, J. C. Robertson
Nuclear Science and Engineering | Volume 94 | Number 3 | November 1986 | Pages 227-232
Technical Paper | doi.org/10.13182/NSE86-A17265
Articles are hosted by Taylor and Francis Online.
The neutron capture cross section in 115In leading to the 54.12 min isomeric state (m1) in 116In has been absolutely determined at neutron energies of 23, 265, and 964 keV. These energies are the median neutron energies of the three photoneutron sources, Sb-Be, Na-D, and Na-Be, applied in this work. The measurements are independent of other cross-section data except for corrections amounting to <10%. Reaction rates were determined by beta counting of the 116m1In decay activity using a 4π gas flow proportional counter. Detector efficiency was measured using 4π beta-gamma coincidence counting techniques, incorporating the foil absorber method of efficiency extrapolation for correction of complex decay scheme effects. Photoneutron source emission rates were determined by indirect comparison with the U.S. National Bureau of Standards NBS-II standard source in the University of Michigan Manganese Bath. The normalized scalar flux was calculated from the neutron emission angular distribution results of a Monte Carlo computer program used to model neutron and gamma transport in the source. Correction factors were applied related to competing reactions, neutron scattering from experiment components, background from room-return neutrons, and differences in the energy spectra of the neutron sources. The absolute cross-section values obtained for the 115In(n, γ)116m1In reaction were 588 ± 11, 196 ± 4, and 203 ± 4 mb at 23, 265, and 964 keV, respectively.
