Fission yields data generation and benchmarks of decay heat estimation of a nuclear fuel
1 Nuclear Data Center, Korea Atomic Energy Research Institute, Daejeon, Republic of Korea
2 Department of Physics, Sungkyunkwan University, Suwon 440–746, Republic of Korea
a e-mail: firstname.lastname@example.org
Published online: 13 September 2017
Fission yields data with the ENDF-6 format of 235U, 239Pu, and several actinides dependent on incident neutron energies have been generated using the GEF code. In addition, fission yields data libraries of ORIGEN-S, -ARP modules in the SCALE code, have been generated with the new data. The decay heats by ORIGEN-S using the new fission yields data have been calculated and compared with the measured data for validation in this study. The fission yields data ORIGEN-S libraries based on ENDF/B-VII.1, JEFF-3.1.1, and JENDL/FPY-2011 have also been generated, and decay heats were calculated using the ORIGEN-S libraries for analyses and comparisons.
© The Authors, published by EDP Sciences, 2017
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