Application of the JENDL-4.0 nuclear data set for uncertainty analysis of the prototype FBR Monju

Konomura, Mamoru; Tamagno, P.*; Van Rooijen, W. F. G.*; Takeda, Toshikazu*

This paper deals with uncertainty analysis of the Monju reactor using JENDL-4.0 and the ERANOS code. A JENDL-4.0 cross-sections library was made from the original ENDF files for the ECCO cell code (part of ERANOS). Calculations for the Monju reactor were performed using hexagonal 3D geometry and PN transport theory. The corresponding geometrical models have been made and the results verified with Monju restart experimental data. Uncertainty analysis was performed using the RZ model.JENDL-4.0 uncertainty analysis showed a significant reduction of the uncertainty related to the fission cross-section of Pu along with an increase of the uncertainty related to the capture cross-section of U compared with the previous JENDL-3.3 version. Covariance data recently added in JENDL-4.0 for Am appears to have a non negligible contribution.