Cross section adjustment for fast reactor design: ATCROSS code and its application

The results of uncertainty analyses performed for the Korean PGSFR reactor are in a good accordance with those already published for the similar designs; thus the calculated target cross section uncertainties could be seen as realistic. The uncertainty of keff induced by cross section data reaches approximately 2%. The uncertainty induced by cross section data for fuel temperature and loss of coolant reactivity feedback effects reach 6% and 13%, respectively. These uncertainties may be reduced by applying the conventional cross section adjustment method in conjunction with sufficient amount of high-quality experimental data. The first application of conventional cross section method to PGSFR core design is introduced in the paper.