Analysis of Recovery Procedures for a Single Steam Generator Tube Rupture

摘要

The LOFT Experiments L6-8C-1 and L6-8C-2 simulated a single steam generator tube rupture, a transient that is likely to occur during the lifetime of a commercial pressurized water reactor (PWR). These experiments were designed to evaluate an alternative procedure for recovery from such an accident, and to evaluate techniques used to analyze reactor transients. Experiment L6-8C-1 was the alternative procedure, conducted with the reactor coolant pumps on while depressurizing the primary coolant system by feed and bleed of the unaffected steam generator, and operation of the pressurizer spray. Experiment L6-8C-2 simulated the standard procedure used in commercial PWRs and was conducted with the reactor coolant system by feed and bleed of the unaffected steam generator, and operation of the power-operated relief valve. The results of the study indicate that the pressurizer spray is as effective as the power operated relief valve. The results of the study indicate that the pressurizer spray is as effective as the power operated relief valve for reducing the primary system pressure, and can be used to reduce the release of primary system coolant to the environment. The results of the posttest calculations agreed very well with the data, and indicated that the RELAP5/MOD1 code could be a capable analytical tool for studying reactor safety problems. (ERA citation 10:008624)