Research On Steam Emission Characteristics Of Secondary Side Of Nuclear Power Unit

Nowadays,the nuclear power industry in China has entered the period of accelerated development.Under the background of the high safety requirements of nuclear power plants,it is an important task to establish a reliable thermal hydraulic model of nuclear power plants and analyze the transient accidents to evaluate their safety.As one of the safety protection systems of nuclear power plant,GCT has an important impact on the thermal hydraulic parameters of the primary side,which is likely to lead to primary side supercooling.The model is based on the M310 nuclear power plant and RELAP5 as modeling tool.Through the induction and simplification of system parameters of nuclear power plant,the modular modeling of nuclear power plant system is carried out.The model includes RCP,RRA,RIS and ASG system.The modular model is integrated into a steady-state system and adjusted to be in accordance with the actual conditions.A reliable steady-state model and parameters are obtained.Based on the steady-state operation,the transient simulation of SBLOCA occurred in the stable operation of the unit is carried out.After LOCA occurred,the GCT can effectively remove the primary circuit heat,and ensure the core temperature is within the safety threshold.The combination of RIS system and RRA system will lead to two-phase instability of coolant in primary circuit,but the core keeps submerged.Long term injection of RIS system can ensure the continuous inundation of the core,and plays an important role in ensuring the safety of the reactor after the accident.