Cladding breaches in mixed oxide fuel pins
Breaches of the cladding have occurred on eleven fuel pins from the HEDL mixed oxide (75 w/o UO/sub 2/ - 25 w/o PuO/sub 2/) irradiation tests in EBR-II. These pins were in 19 or 37 pin subassemblies being irradiated as part of the HEDL Steady State and Run-to-Cladding Breach activities for the FFTF Reference Fuel Program. The linear powers and temperatures of these tests were within the FFTF Steady State design envelopes. Cladding materials included solution-annealed type 304 and 20 percent or 30 percent cold-worked type 316 stainless steel. All pins were fabricated to the reference specifications current at the time for the FFTF driver fuel, except for those with the 30 percent cold-worked cladding. The objectives of the studies and examinations of the breached pins are to: (1) establish the burnup capability for reference fuel, (2) identify cladding breach mechanisms, (3) determine the effects of cladding breach on neighboring fuel pins, (4) evaluate the effects of short term postbreach residence in reactor on fuel-coolant interaction, and (5) provide data for failure criteria. Examination and characterization have been completed on nine of the eleven breached pins, with two pins currently being examined. In addition, 46 neighbors to the breached pins have been evaluated for possible effects as a consequence of the breach.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 6718187
- Report Number(s):
- HEDL-SA-1299-S; CONF-771109-104
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
EPITHERMAL REACTORS
FAST REACTORS
FFTF REACTOR
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
LIQUID METAL COOLED REACTORS
PERFORMANCE TESTING
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SODIUM COOLED REACTORS
TEST REACTORS
TESTING