LWR fuel rod behavior observed during postulated accident conditions: a comparison of FRAP-T calculated and PBF experimental results
Light water reactor (LWR) fuel rod behavior during transient experiments conducted in the Power Burst Facility is reviewed. The experiments examined simulated hypothetical reactivity initiated accidents (RIA) and power-cooling-mismatch (PCM) events. Fuel rod behavior calculated by the Fuel Rod Analysis Program-Transient (FRAP-T) is compared with the test data. Important physical phenomena observed during the tests and not presently incorporated into the FRAP-T code are: (a) fuel swelling in the radial direction due to fission gas effects, (b) UO/sub 2/-zircaloy chemical interaction, and (c) loss of UO/sub 2/ grain boundary strength and fuel powdering. Additional models needed in FRAP-T to reflect the fuel behavior observed during the two types of transients are cladding thickness variation during an RIA, molten fuel movement and possible cladding-molten fuel thermal interaction during a PCM event, and in the case of breached rods, the effects of hydrogen pickup on cladding embrittlement.
- Research Organization:
- Idaho National Engineering and Environmental Laboratory (INEEL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USNRC
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5378926
- Report Number(s):
- CONF-800403-26; TRN: 80-008553
- Resource Relation:
- Conference: ANS thermal reactor safety meeting, Knoxville, TN, USA, 8 Apr 1980
- Country of Publication:
- United States
- Language:
- English
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