ABSTRACT
To validate the nuclear data in JENDL-4.0 and obtain information to improve their accuracy, the analysis of the measured nuclide inventories of the high-burnup PWR UO2 and BWR MOX fuels in the REBUS program was performed by using MVP-BURN with the nuclear library and burnup chain based on JENDL-4.0, and the ratios of the calculated and measured inventories (C/Es) were compared with the previous results obtained with JENDL-3.2 or JENDL-3.3. As a result, an improvement in the accuracy of the neutron cross-sections and cumulative fission yields (CFYs) in JENDL-4.0 was confirmed for the inventories of 236U, 238Pu, 239Pu, 241Pu, 242Pu, 241Am, 243Cm, 244Cm, 133Cs, 145Nd, 148Sm, 149Sm, 151Sm, and 153Eu of the PWR UO2 fuel and 239Pu, 241Pu, 242Pu, 241Am, 243Am, 243Cm, 244Cm, 246Cm, 134Cs, 144Ce, 145Nd, 147Sm, and 154Eu of the BWR MOX fuel. Based on the C/Es obtained with JENDL-4.0, the directions to improve the neutron cross-sections and CFYs were tentatively proposed. They included the neutron capture cross-sections of 234U, 236U, 237Np, 238Pu, 241Am, 242Cm, 245Cm, 143Nd, 147Pm, 154Eu, and 155Eu, the fission cross-sections of 243Cm and 245Cm, and the CFYs of 144Nd, 147Pm, and 155Eu.
Disclosure statement
No potential conflict of interest was reported by the author.
Supplementary material
Supplemental data for this article can be accessed online at https://doi.org/10.1080/00223131.2023.2290068
Notes
1. Reactivity test for a direct evaluation of the burnup credit on selected irradiated LWR fuel bundles.
2. Gemeinschaftskernkraftwerk Unit II in Neckarwestheim.