JENDL-5 benchmarking for fission reactor applications

Tada, Kenichi; Nagaya, Yasunobu; Taninaka, Hiroshi; Yokoyama, Kenji; Okita, Shoichiro; Oizumi, Akito; Fukushima, Masahiro; Nakayama, Shinsuke

Journal of Nuclear Science and Technology, 21 Pages, 2023/04

https://doi.org/10.1080/00223131.2023.2197439

The new version of the Japanese evaluated nuclear data library, JENDL-5, was released in December 2021. This paper demonstrates the validation of JENDL-5 for fission reactor applications. Benchmark calculations are performed with the continuous-energy Monte Carlo codes MVP and MCNP and the deterministic code system MARBLE. The benchmark calculation results indicate that the performance of JENDL-5 for fission reactor applications is better than that of the former library JENDL-4.0.

Proceedings of the 1992 Symposium on Nuclear Data; November 26-27, 1992, JAERI, Tokai, Japan

Baba, Mamoru*; Nakagawa, Tsuneo

JAERI-M 93-046, 379 Pages, 1993/03

JAERI-M-93-046.pdf:10.45MB

no abstracts in English

Proceedings of the 1985 Seminar on Nuclear Data

Asami, Tetsuo;

JAERI-M 86-080, 429 Pages, 1986/06

JAERI-M-86-080.pdf:10.06MB

no abstracts in English

Reactor benchmark tests for JENDL-5

Tada, Kenichi

no journal, , 

The latest version of Japanese Evaluated Nuclear Data Library, JENDL-5, was released in December of 2021. To investigate the prediction accuracy of JENDL-5 for criticality of reactor cores, we performed benchmark tests by using the International Criticality Safety Benchmark Evaluation Project (ICSBEP) handbook. Judging from the overall results, we confirmed that JENDL-5 gave the better results than JENDL-4.0. The burn-up calculations using JENDL-5 for LWR pin cell and assembly geometries were also carried out and the calculation results were compared to the other nuclear data libraries. The calculation results indicate that the differences of Pu-239, Gd-155, and Gd-157 affect the burn-up calculations.