ANALYSIS OF STEAM GENERATOR TUBE RUPTURE IN HTR-MODUL REACTOR

摘要

The RELAP5-3D code was used to model the HTR-MODUL reactor and analyze an event of a single steam generator tube rupture (SGTR), proceeding with, or without operator intervention, or actuation of any reactor protection. Four cases have been analyzed to evaluate the impact from mitigation actions and from the location of the steam generator (SG) tube break on reactor power, primary coolant pressure, and mass of vapor in the core. The simulation results provide a basis for evaluating the magnitude of challenges to plant safety as reactor overpower, reactor coolant system (RCS) over-pressure, and release of radioactive nuclides from the primary system.