TRAC-PD2 analysis of a large-break loss-of-coolant accident in a typical US PWR

Technical Report · Tue Jun 01 04:00:00 EDT 1982

OSTI ID:5163046

Ireland, J R

A 200% double-ended cold-leg break loss-of-coolant accident (LOCA) in a typical US pressurized water reactor (PWR) was simulated using the Transient Reactor Analysis Code (TRAC-PD2). The reactor system modeled represented a typical US PWR with four loops (three intact, one broken) one cold-leg emergency-core-cooling system (ECCS). The finely noded TRAC model employed 440 three-dimensional (r, o, z) vessel cells along with approximately 300 one-dimensional cells that modeled the primary system loops. The calculated peak cladding temperature of 950 K occurred blowdown and the cladding temperature excursion was terminated at 175 s, when complete core quenching occurred. Accumulator flows were initiated at 10 s, when the system pressure reached 4.08 MPa, and the refill phase ended at 36 s, when the lower plenum refilled. During reflood, both bottom and falling film quench fronts were calculated.

• Research Organization: Los Alamos National Lab., NM (USA)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5163046
• Report Number(s): NUREG/CR-2775; LA-9411-MS; ON: DE82019479
• Country of Publication: United States
• Language: English

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