Further experimental results of the irradiation of long-rod duplex-pellet screening tests in the NRX reactor (NLDR-2/3/4 tests)
The duplex pellet concept waeither a principal area of investigation in the Advanced Water Breeder Applications (AWBA) program at the Bettis Laboratory. A duplex pellet consists of a cylindrical ThO/sub 2/ central pellet (fertile material) inside an oxide annulus of either UO/sub 2/, UO/sub 2/-ThO/sub 2/, or UO/sub 2/-ZrO/sub 2/-CaO (fissile material). The NLDR-2/3/4 test was one of several screening irradiation tests performed to investigate the behavior of duplex pellets. It consists of four 110-inch-long, 0.3-inch-diameter, Zircaloy-4 clad rods containing duplex pellets. Three rods contained UO/sub 2/ annuli. The fourth rod contained ThO/sub 2/-UO/sub 2/ annuli. All rods were irradiated in pressurized water loops in the NRX reactor to peak depletions. This report presents a description of the test rods and irradiation history and results of nondestructive examinations. Annulus composition and fuel dimensional changes, which were relatively small for all four rods.
- Research Organization:
- Bettis Atomic Power Lab., Pittsburgh, PA (USA)
- DOE Contract Number:
- AC11-76PN00014
- OSTI ID:
- 5757336
- Report Number(s):
- WAPD-TM-1520; ON: DE83017659
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
FUEL PELLETS
PERFORMANCE TESTING
LWBR TYPE REACTORS
REACTOR MATERIALS
PHYSICAL RADIATION EFFECTS
THORIUM OXIDES
URANIUM DIOXIDE
BURNUP
SWELLING
ZIRCALOY 4
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CHALCOGENIDES
MATERIALS
OXIDES
OXYGEN COMPOUNDS
PELLETS
RADIATION EFFECTS
REACTORS
TESTING
THERMAL REACTORS
THORIUM COMPOUNDS
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210500* - Power Reactors
Breeding
360206 - Ceramics
Cermets
& Refractories- Radiation Effects