https://doi.org/10.1051/epjconf/201714604048
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: csgil@kaeri.re.kr
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
This is an Open Access article distributed under the terms of the Creative Commons Attribution License 4.0, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
