Results of the Semiscale Mod-2B Steam Generator Tube Rupture Test Series.

摘要

A series of experiments was conducted in a scaled model of a pressurized water reactor to investigate steam generator tube rupture system signature response and recovery techniques. The tube rupture was assumed to occur during normal full power operation. From the experimental results, the characteristic system signature responses for a wide range of number of tubes ruptured and rupture locations have been examined. In addition, recovery techniques requiring operator actions were examined. These recovery techniques included the use of pressurizer auxiliary spray and internal heaters, steam generator feed and steam, primary feed and bleed, and safety injection. The effectiveness of using these techniques for primary system pressure and subcooling control is discussed.