Experiment data report for Semiscale Mod-1 Test S-29-2 (integral test from reduced pressure). [PWR]

Technical Report · Sun Aug 01 04:00:00 EDT 1976

DOI:https://doi.org/10.2172/7246826· OSTI ID:7246826

Crapo, H. S.; Sackett, K. E.

Recorded test data are presented for Test S-29-2 of the Semiscale Mod-1 special heat transfer test series. This test is among several Semiscale Mod-1 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor system. The test was conducted from an initial cold leg fluid temperature of 544/sup 0/F and an initial pressure of 1,760 psia. A simulated double-ended offset shear cold leg break was used to investigate the system response to a depressurization transient starting from a lower initial pressure than that usually associated with pressurized water reactor operation. System flow was set to achieve a full-core temperature differential of 66/sup 0/F at a full core power of 1.6 MW. The flow resistance of the intact loop was based on core area scaling. An electrically heated core with a flat radial power profile was used in the pressure vessel to simulate the effects of a nuclear core. During system depressurization, core power was reduced from the initial level of 1.6 MW to simulate the surface heat flux response of nuclear fuel rods until such time as departure from nucleate boiling might occur.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• DOE Contract Number: E(10-1)-1375
• OSTI ID: 7246826
• Report Number(s): ANCR-NUREG-1328
• Country of Publication: United States
• Language: English

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