关键词:核电,Fluent,事故 简介:Engineers at the Nuclear Regulatory Commission (NRC) have used CFD to predict the risk of temperature-induced rupture during severe nuclear reactor accidents. In a recent project, CFD was used to predict the details of mixing in the steam generator inlet plenum during a severe accident sequence in which secondary side cooling is lost, and superheated vapor circulates through the reactor system. Since the core is uncovered, heat is carried away from the fuel by steam in a process of natural circulation. The steam carries the heat to structures in the reactor coolant system, including the upper vessel, hot leg, and steam generator tubes. In this scenario, the loop seals are filled with water and the primary loop circulation is blocked, conditions that ultimately lead to a failure in the primary coolant loop. The flow field and heat transfer details determine whether this failure occurs in the reactor coolant piping (within containment) or in the steam generator tubing (with a leak path out of containment). |