Examination of a failed rod operating with molten UO/sub 2/--ZrO/sub 2/--CaO fuel (LWBR Development Program)
Technical Report
·
OSTI ID:6761405
A 0.250-inch diameter Zircaloy-4 sheathed fuel rod containing dished-end pellets of ZrO/sub 2/ + 6.1 wt % CaO + 33.2 wt % UO/sub 2/ operated at high heat fluxes and with approximately half of the fuel volume in the molten state. It is postulated that contact between molten fuel and the tubing resulted in burn-through and rod failure. The rod operated at full power for 25 minutes after failure, which was sufficient time for intensive hydriding of the cladding to occur. (NSA 21: 17539)
- Research Organization:
- Bettis Atomic Power Lab., Pittsburgh, PA (USA)
- DOE Contract Number:
- AT(11-1)-GEN-14
- OSTI ID:
- 6761405
- Report Number(s):
- WAPD-TM-593
- Country of Publication:
- United States
- Language:
- English
Similar Records
Irradiation performance capabilities of oxide fuel rods X-1-u test of two 100-inch long highly rated annular ZrO/sub 2/ + UO/sub 2/ fuel rods (LWBR Development Program)
Short-term irradiation of Zircaloy-4 clad fuel rods containing low-density or annular ZrO/sub 2/--UO/sub 2/ ceramic fuel pellets: X-1-t test (LWBR Development Program)
Observations on the irradiation behavior of a Zircaloy-4 clad rod containing low density ThO/sub 2/--5. 3 wt. percent UO/sub 2/ pellets (LWBR Development Program)
Technical Report
·
Thu Sep 01 00:00:00 EDT 1966
·
OSTI ID:6761429
Short-term irradiation of Zircaloy-4 clad fuel rods containing low-density or annular ZrO/sub 2/--UO/sub 2/ ceramic fuel pellets: X-1-t test (LWBR Development Program)
Technical Report
·
Sat Jun 01 00:00:00 EDT 1968
·
OSTI ID:6747393
Observations on the irradiation behavior of a Zircaloy-4 clad rod containing low density ThO/sub 2/--5. 3 wt. percent UO/sub 2/ pellets (LWBR Development Program)
Technical Report
·
Sun Nov 30 23:00:00 EST 1969
·
OSTI ID:7010703
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
ACCIDENTS
ACTINIDE COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
ALLOYS
BREEDER REACTORS
BURNOUT
CALCIUM COMPOUNDS
CALCIUM OXIDES
CHALCOGENIDES
FUEL ELEMENT FAILURE
FUEL ELEMENTS
LWBR TYPE REACTORS
MELTDOWN
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
220300* -- Nuclear Reactor Technology-- Fuel Elements
ACCIDENTS
ACTINIDE COMPOUNDS
ALKALINE EARTH METAL COMPOUNDS
ALLOYS
BREEDER REACTORS
BURNOUT
CALCIUM COMPOUNDS
CALCIUM OXIDES
CHALCOGENIDES
FUEL ELEMENT FAILURE
FUEL ELEMENTS
LWBR TYPE REACTORS
MELTDOWN
OXIDES
OXYGEN COMPOUNDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
THERMAL REACTORS
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS