Comparison of TRAC-PD2 calculations to emergency-core-coolant bypass data

Conference · Fri Jan 01 04:00:00 EST 1982

OSTI ID:6977614

Meier, J K

The Los Alamos Transient Reactor Analysis Code, TRAC-PD2, is a multidimensional thermal-hydraulic computer code that can simulate loss-of-coolant accidents (LOCAs) in pressurized-water reactors (PWRs). As part of our independent assessment of this code, we compared TRAC calculated results with Battelle Columbus Laboratories (BCL) test data. We based our comparisons on the BCL downcomer countercurrent flow test that used a 2/15-scale model of a coreless PWR vessel. In general, TRAC tended to underpredict the steam flow necessary to prevent significant flooding of the downcomer. This underprediction is insignificant in low-subcooling cases; however, in high-subcooling cases, the steam flows for similar degrees of water penetration were 30 to 35% less in the TRAC predictions than in the test data. Thus, we infer that the calculations for the momentum transfer between the two phases were adequate, but that the interfacial heat-transfer correlations could use improvement. 14 figures.

• Research Organization: Los Alamos National Lab., NM (USA)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 6977614
• Report Number(s): LA-UR-82-1787; CONF-830103-3; ON: DE82017332
• Country of Publication: United States
• Language: English

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