NUCLEAR REACTOR CORE ASSESSMENT METHOD USING THERMAL HYDRAULIC SAFETY ANALYSIS CODE

摘要

PURPOSE: A nuclear reactor core assessment method using a thermal hydraulic safety analysis code is provided to evaluate a reactor core through single code system by modeling a vapor supply system, the hot water pipe of the reactor core, and the high temperature point of the reactor core. CONSTITUTION: In a nuclear reactor core assessment method using a thermal hydraulic safety analysis code, a model of a vapor supply system model is generated(101). A model of the hot water pipe of the reactor core is generated(103). A model of the high temperature of the reactor core is generated(105). The temperature, pressure, and flow rate of the vapor supply system is calculated(107). The heat output and heat flux, or nucleate boiling ratio breakaway rate of the hot water pipe of the reactor core are calculated. The high temperature point distribution of the reactor core and average enthalpy in radial direction or the maximum temperature of a covering material are calculated(109) nucleate boiling ratio breakaway rate or average enthalpy in radial direction is analyzed(111) A model of the high temperature water pipe of the reactor core is generated.