Validation of SOCRAT-BN code on the base of reactor experiments

SOCRAT-BN code is developed for safety assessment for Liquid Metal Fast Breeder Reactors (LMFBR) with sodium coolant during the design basis accidents and beyond design-basis accidents. Code consists of the several modules, which allows simulating: thermal hydraulic, neutron-physic, thermal-mechanical processes and behavior of fission products in rector vessel in coupled statement. Brief description of SOCRAT-BN code is presented in the paper. Validation on the base of the integral experiments and out-of-pile experiments were carried out to show code workability. Integral tests include experiments provided at BN-600 reactor. Detailed nodalization scheme, consists of primary, secondary and third sides, was performed to simulate BN-600 reactor. To validate SOCRAT-BN code the following BN-600 transients were chosen: natural circulation core cooling at 50% power load, and one loop tripping at about 100% power load. SOCRAT-BN code simulations results showed good agreement with the experimental data. (author)