Impact of nuclear data revised from JENDL-4.0 to JENDL-5 on PWR spent fuel nuclide composition

ABSTRACT

The burnup calculations for estimating the nuclide composition of the spent fuel are highly dependent on nuclear data. Many nuclides in the latest version of the Japanese Evaluated Nuclear Data Library JENDL-5 were modified from JENDL-4.0 and the modification affects the burnup calculations. This study confirmed the validity of JENDL-5 in the burnup calculations. The PIE data of Takahama-3 was used for the validation. The effect of modifications of the parameters, e.g. cross sections and fission yields, from JENDL-4.0 to JENDL-5 on the nuclide compositions was quantitatively investigated. The calculation results showed that JENDL-5 has a similar performance to JENDL-4.0. The calculation results also revealed that the modifications of the cross sections of actinide nuclides, fission yields, and thermal scattering low data of hydrogen in H₂O affected the nuclide compositions of PWR spent fuels.

KEYWORDS:

• JENDL-5
• JENDL-4.0
• burnup calculation
• validation
• PIE
• PWR

Acknowledgments

The authors wish to express their gratitude to Dr. K. Suyama for advice on the burnup calculation condition of Takahama-3 PIE data. The authors wish to express their gratitude to Mr. T. Kikuchi for helping prepare the computing environment and input files of Serpent 2.

Disclosure statement

No potential conflict of interest was reported by the author(s).

Supplementary material

Supplemental data for this article can be accessed online at https://doi.org/10.1080/00223131.2023.2201603