JNC results of BN-600 hybrid core benchmark calculations

This paper presents the phase 1 calculation results of the benchmark core of the BN-600 reactor. The analytical method applied included the following: JENDL-3.2 nuclear data library; 70 group ABBN type self shielding factor table for group constants; reference delayed neutron yield and spectrum adopted; effective cross section obtained by SLAROM code; basic calculation done by using 18 group two dimensional RZ model (CITATION code) with region dependent fission spectra; transport theory and mesh size correction (TWOTRAN code); perturbation calculation done by diffusion, first order perturbation reactivity mapping method (PERKY code). Calculation results include effective multiplication factors; fuel Doppler constants; steel Doppler constants; sodium density coefficient; steel density coefficients; fuel density coefficient; absorber density coefficient; axial and radial expansion coefficients; dynamic parameters; power distribution; beta and neutron life time; reaction rate distribution