A series of pipe rupture tests have been performed at the Japan Atomic Research Energy Institute to demonstrate the safety of the primary coolant circuits in the event of pipe rupture in nuclear power plants. Pipe whip tests and jet discharge tests have been conducted under the BWR and PWR LOCA conditions. The results of the pipe whip tests using 4, 6 and 8 inch test pipes under the BWR LOCA conditions were reported in the previous paper. The present paper describes the experimental and analytical results of the pipe whip tests performed under the PWR LOCA conditions using 4, 6 and 8 inch test pipes. The tests were carried out at an initial pressure and a temperature of 15.7MPa and 325°C.
Two different types of tests were performed. One was the cantilever type pipe whip test using the test pipe of 3000mm in length and U-shaped restraints. The other was the crossover leg pipe whip test using a 1/6 model of piping in the PWR nuclear power plants.
The cantilever type pipe whip tests were performed to investigate the influences of overhang length and pipe diameter on the pipe whip behavior. The movement of the test pipe is limited effectively by the restraints when the overhang length is short. The restraint force increases in proportion to the breaking area.
The crossover leg pipe whip test was performed to demonstrate the integrity of the restraints at the LOCA. Strain-gages, accelerometers and load cells were used to measure the dynamic response of the test pipe. Test results showed that the deformation of the restraints were within elastic limit, and the residual deformation at a free end was 6.7mm.
The dynamic structural analysis of pipe whip tests was carried out using the general purpose finite element program ADINA. Damping factor of the restraint was attached to the truss element to improve the transient response, of the restraint force. Analytical results using this finite element model were approximately coincident with the results of 6 inch pipe whip test.
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