Comparisons of TRAC-PD2 calculations with Semiscale Mod-3 small-break tests. [PWR]

Conference · Thu Jan 01 04:00:00 EST 1981

OSTI ID:6463583

Gilbert, J S; Sahota, M S; Boyack, B E; Booker, C P; Meier, J K

Five experiments conducted in the Semiscale Mod-3 facility at the Idaho National Engineering Laboratory (INEL) were calculated using the latest released version of the Transient Reactor Analysis Code (TRAC-PD2). The results were used to assess TRAC-PD2 predictions of thermal-hydraulic phenomena and the effects of pump operation on system response during slow transients. Tests S-SB-P1, S-SB-P2, and S-SB-P7 simulated equivalent 2.5% communicative cold-leg breaks for early pump-trip (pumps-off), intermediate pump-trip (pumps-on), and late pump-trip (pumps-on) operation, respectively. Tests S-SB-P3 and S-SB-P4 simulated equivalent 2.5% communicative hot-leg breaks for pumps-off and pumps-on operation, respectively. Parameters examined in the study included primary system mass distribution, mass inventory, and void fraction distribution.

• Research Organization: Los Alamos National Lab., NM (USA)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6463583
• Report Number(s): LA-UR-81-1520; CONF-810806-4
• Country of Publication: United States
• Language: English

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