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Applicability of JENDL-5 to Tihange Unit 2 Reactor Core Analysis

Shigeki Shiba

Nuclear Technology / Volume 212 / Number 6 / June 2026 / Pages 1623-1639

Regular Note / dx.doi.org/10.1080/00295450.2025.2502262

Received:September 3, 2024
Accepted:April 22, 2025
Published:May 15, 2026

The fifth version of the Japanese Evaluated Nuclear Data Library (JENDL-5) was released in December 2021. It is essential to validate JENDL-5 using the reactor core analysis data of light water reactors and to evaluate the performance of JENDL-5 in comparison with other major nuclear data libraries, namely, JENDL-4.0, ENDF/B-VIII.0, and ENDF/B-VII.1. In this paper, reactor core analyses of Tihange-2, which is a three-loop 900-MW(electric) Framatome pressurized water reactor, were performed using CASMO5/SIMULATE5. The results indicated that the radial power distributions were accurately simulated using JENDL-5, but discrepancies in the critical boron concentration during cycle burnups were observed. The main cause of these discrepancies was found to be low reactivity caused by the 239Pu reaction cross section in JENDL-5. Accordingly, further validation and code updates are expected in applying the library to core analyses of light water reactors.