High-level radiation field analysis using Monte Carlo simulation in KORI nuclear power plant unit 1

It is requested basically to make certain safety information about distribution of radiation field inside nuclear power plant. It was performed to analysis of radiation field in KORI unit 1 cycle 20 by using the modeling and construction of calculation system. By using the function of MCNP code, calculation system was constructed to divide source term and the others, the inside of plant, and modeling was performed for KORI nuclear power plant unit 1. Calculation system and modeling was verified using these for circumstance in cycle 20 and analysis of distribution of radiation field was performed from source term. First, source term that had been verified for practical reactor core about 2.96% of error was calculated. Neutron spectrum was evaluated for six points of inside of containment building. Calculated value are with real detected value, neutron spectrum, it was conformed. At last it was tested by evaluating the fluence the level of radiation field. It was calculated at two points near the boundary of steam generator and and one point of of room of steam generator. 1.327X103 neutrons/cm2sec, 1.874x103 neutrons/cm2sec, 1.002 neutron/cm2sec are evaluated in maximum at the level of 20ft. 4.587x103 neutrons/cm2sec, 4.579x103 neutrons/cm2sec, 20.63 neutrons/cm2sec, 20.63 neutrons/cm2sec are evaluated for same points at the level of 44ft