Preliminary Assessment of Open Reactor Physics Database for Cross Section Adjustment

The uncertainty of nuclear data occupies a considerable portion in a fast reactor analysis compared with other uncertainty arising from analysis methodology, geometrical approximation. Korea Atomic Energy Research Institute (KAERI) is now developing a cross section adjustment method for enhancing a sodium cooled fast reactor (SFR) design. In order to get an appropriate accuracy from the cross section adjustment, many measured integral parameters are necessary. Unfortunately, the design feature in SFR that has been developed in KAERI is quite different from that had been validated so far. The main difference in design arises from the use of metallic fuel, which make harder neutron spectrum than that of oxide fueled core. The reactor physics database on metal fuel loaded core is very limited number and a new experiment is very costly. In this context, KAERI considers the use of open reactor physics database in the cross section adjustment in addition to the own reactor physics experiment. Although the open reactor physics data are almost for the oxide core, it is considered to be partially used in the cross section adjustment. The main purpose of this study is to assess the open reactor physics database for inclusion of the cross section adjustment procedure