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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.
C. Tsabaris, E. Wattecamps, G. Rollin, C. Papadopoulos
Nuclear Science and Engineering | Volume 128 | Number 1 | January 1998 | Pages 47-60
Technical Paper | doi.org/10.13182/NSE128-47
Articles are hosted by Taylor and Francis Online.
Double-differential (n,xp) and (n,x) cross-section ratio measurements are performed at the 7-MV Van de Graaff accelerator laboratory for neutron energies between 2.0 and 15.6 MeV. The following reaction rate ratios are measured: 58Ni(n,x) to 27Al(n,), 58Ni(n,x) to 58Ni(n,p), 63Cu(n,xp) to 27Al(n,), and 63Cu(n,xp) to 58Ni(n,p). Protons or alphas are detected by E-E-E telescopes under 14, 51, 79, 109, and 141 deg. The energy spectrum of the emitted particles and the angular yield distribution are measured. First, the measurements provide double-differential cross-section data for 27Al(n,) and 58Ni(n,p) by normalization to the known total yield reference cross-section values. Subsequently, the reaction rate ratios of 58Ni(n,x) and 63Cu(n,xp) to 27Al(n,) or 58Ni(n,p) provide double-differential cross sections of 58Ni(n,x) and 63Cu(n,xp) in b/(MeVsr). The measured double-differential cross-section data, the particle energy spectra, the angular distributions, and the total yield cross-section data are compared with measured data from literature and with nuclear reaction model calculations performed at the Institute for Reference Materials and Measurements with the computer codes STAPRE-H and EXIFON.