FRAP-T5 predictions during reactor shutdown events. [PWR; BWR]

Conference · Tue Jan 01 00:00:00 EST 1980

OSTI ID:5553368

Peeler, G. B.; Laats, E. T.

The Transient Fuel Rod Analysis Program, FRAP-T5, was recently assessed by EG and G Idaho, Inc. As part of this assessment, the measured and FRAP-T5 predicted fuel centerline temperature response during reactor shutdown events were compared. For these events either forced convection or nucleate boiling boundary conditions existed, resulting in a negligible effect on fuel behavior from cladding temperature and deformation uncertainties. This allowed the assessment of internal heat transfer to be emphasized.

• Research Organization: Idaho National Engineering Lab., Idaho Falls (USA)
• Sponsoring Organization: USDOE
• DOE Contract Number: EY-76-C-07-1570
• OSTI ID: 5553368
• Report Number(s): CONF-800607-13; TRN: 80-007960
• Resource Relation: Conference: American Nuclear Society annual meeting, Las Vegas, NV, USA, 8 Jun 1980
• Country of Publication: United States
• Language: English

Related Subjects

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