Experimental results of the irradiation of long rod duplex pellet screening tests in the NRX reactor (NLDR-1 test) (AWBA Development Program)
Technical Report
·
OSTI ID:6654046
One of the principal areas of investigation in the Advanced Water Breeder Applications (AWBA) program at the Bettis Laboratory is the duplex pellet concept. 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-1 test is one of several screening irradiation tests performed to investigate the behavior of duplex pellets. It consists of two 110-inch long, 0.3 inch diameter, Zircaloy-4 clad rods containing duplex pellets. One rod contained UO/sub 2/ annuli. The other rod contained UO/sub 2/-ZrO/sub 2/-CaO annuli. Both rods were irradiated in pressurized water loops in the NRX reactor to peak depletions of 76,000 MWd/MT U + TH (UO/sub 2/ rod) and 120,000 MWd/MT U + Th (UO/sub 2/-ZrO/sub 2/CaO rod) and average depletions of about 63,000 MWd/MT and about 100,000 MWd/MT, respectively. Peak linear power outputs were 15.3 kW/ft (UO/sub 2/ rod) and 13.9 kW/ft (UO/sub 2/-ZrO/sub 2/-CaO rod). Both rods were periodically removed from the reactor for nondestructive examinations.
- Research Organization:
- Bettis Atomic Power Lab., Pittsburgh, PA (USA)
- DOE Contract Number:
- AC11-76PN00014
- OSTI ID:
- 6654046
- Report Number(s):
- WAPD-TM-1492; ON: DE83001849
- Country of Publication:
- United States
- Language:
- English
Similar Records
Further experimental results of the irradiation of long-rod duplex-pellet screening tests in the NRX reactor (NLDR-2/3/4 tests)
Irradiation performance of long-rod duplex fuel-pellet bundle test - LDR test (AWBA Development Program)
Irradiation performance of duplex-fuel-pellet test rods depleted to 9 x 10/sup 20/ fissions/cm/sup 3/ of compartment: D-1 test (AWBA development program)
Technical Report
·
Fri Oct 01 00:00:00 EDT 1982
·
OSTI ID:5757336
Irradiation performance of long-rod duplex fuel-pellet bundle test - LDR test (AWBA Development Program)
Technical Report
·
Wed Mar 31 23:00:00 EST 1982
·
OSTI ID:5041799
Irradiation performance of duplex-fuel-pellet test rods depleted to 9 x 10/sup 20/ fissions/cm/sup 3/ of compartment: D-1 test (AWBA development program)
Technical Report
·
Thu Dec 31 23:00:00 EST 1981
·
OSTI ID:6887014
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360206 -- Ceramics
Cermets
& Refractories-- Radiation Effects
ACTINIDE COMPOUNDS
ALLOYS
ANNULAR FUEL ELEMENTS
BREEDER REACTORS
CHALCOGENIDES
DEFORMATION
FUEL ELEMENTS
FUEL PELLETS
FUEL-CLADDING INTERACTIONS
LWBR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
PELLETS
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
TESTING
THERMAL REACTORS
THORIUM COMPOUNDS
THORIUM OXIDES
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210500* -- Power Reactors
Breeding
36 MATERIALS SCIENCE
360206 -- Ceramics
Cermets
& Refractories-- Radiation Effects
ACTINIDE COMPOUNDS
ALLOYS
ANNULAR FUEL ELEMENTS
BREEDER REACTORS
CHALCOGENIDES
DEFORMATION
FUEL ELEMENTS
FUEL PELLETS
FUEL-CLADDING INTERACTIONS
LWBR TYPE REACTORS
OXIDES
OXYGEN COMPOUNDS
PELLETS
PERFORMANCE TESTING
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTOR COMPONENTS
REACTORS
TESTING
THERMAL REACTORS
THORIUM COMPOUNDS
THORIUM OXIDES
TIN ALLOYS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS