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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.
Kokoo, Isao Murata, Akito Takahashi
Nuclear Science and Engineering | Volume 132 | Number 1 | May 1999 | Pages 16-29
Technical Paper | doi.org/10.13182/NSE99-A2046
Articles are hosted by Taylor and Francis Online.
A two-dimensional energy and time-of-flight charged-particle spectrometer has been developed and used to measure the double-differential cross-section (DDX) data of (n, xp) and (n, x) reactions for several elements with 14.1-MeV incident neutrons at OKTAVIAN, the Intense 14-MeV Neutron Source Facility of Osaka University. The DDX data of the 51V(n, xp), 51V(n, x), natFe(n, xp), natFe(n, x), 59Co(n, xp), 59Co(n, x), natNi(n, x), natCu(n, x), 93Nb(n, xp), 93Nb(n, x), and natMo(n, xp) reactions are measured. The angle-integrated energy differential cross-section (EDX) data were deduced from the measured DDX data and compared with other experimental results [except for the 59Co(n, xp) reaction] and evaluated nuclear data of JENDL fusion file (JENDL-FF). A comparison was also done with the ENDF/B-VI for the total reaction cross sections of all measured reactions except for the natMo(n, xp) reaction and the EDX of the natNi(n, x) and natCu(n, x) reactions. The theoretical calculations were done by using the SINCROS-II code. The measured data agreed fairly well with other data for almost all the reactions. The JENDL-FF and SINCROS-II data underestimate the measured EDX data for the reactions of 93Nb(n, x) and natMo(n, xp). For the natFe(n, xp), natFe(n, x), 59Co(n, x), and natNi(n, x) reactions, smaller data are given than other data, i.e, other experimental data, JENDL-FF, and ENDF/B-VI. The SINCROS-II code can reproduce well for both the proton and alpha-particle emission cross-section values.