LWR fuel rod behavior observed during postulated accident conditions: a comparison of FRAP-T calculated and PBF experimental results
Conference
·
OSTI ID:5378926
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:
- NRC
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 5378926
- Report Number(s):
- CONF-800403-26
- Country of Publication:
- United States
- Language:
- English
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