Reactor Physics Experiment on a Graphite-Moderated Core to Construct Integral Experiment Database for HTGR

In this paper, integral experiments on a graphite-moderated core were conducted at the B-rack of the Kyoto University Criticality Assembly in order to develop an integral experiment database for the applicability of data assimilation techniques to the neutronic design of a high-temperature gas-cooled reactor. The calculation/experiment-1 (C/E-1)values for the k(eff) values at critical cores with the major nuclear data libraries, such as JENDL-4.0, JENDL-5, JEFF-3.2, ENDF/B-VII.1, and ENDF/B-VIII.0, were calculated for the core. Of these, the k(eff) values with JENDL-5 with thermal neutron scattering law data for 30% porous graphite showed the best agreement with experimental values within 0.02% accuracy.