Analysis of the Neutronic Properties of the Prototype FBR Monju Based on Several Evaluated Nuclear Data Libraries

Abstract In this work three major evaluated nuclear data libraries (JENDL-4.0, JEFF-3.1.2, ENDF/B-VII.1) are used to analyze the prototype FBR Monju. Cross section libraries were generated for the fast reactor analysis code ERANOS. The purpose is to validate our ERANOS libraries, the Monju core model and estimate the performance of the nuclear data sets. The result is that the libraries give adequate performance for applications where a reasonable accuracy is sufficient (e.g. conceptual design, scoping studies), with JENDL-4.0 giving the best results. The uncertainties of various reactor parameters are larger than the future target values for FBR analysis. For analysis with very high accuracy (e.g. detailed design, licensing), data adjustment is necessary.