Linear heat rating for incipient fuel melting in UO/sub 2/--PuO/sub 2/ fuel
Conference
·
OSTI ID:6786498
Results are presented for an experiment (HEDL-P-19) conducted in EBR-II to determine the effect of the initial, cold, diametral fuel-cladding gap size (3.2 to 10.0 mils) on the linear heat rating to incipient fuel melting, Q/sub m/, in mixed oxide (75% UO/sub 2/--25% PuO/sub 2/) fuel pins under very rapid LMFBR startup conditions. Eight 0.250 in. OD X 0.016 in. wall and eight 0.230 in. OD X 0.015 in. wall, He bonded pins clad with type 316 stainless steel (20% CW) were irradiated in an encapsulated pin subassembly in Row 2 of the EBR-II. Each fuel pellet was measured to +- 0.2 mil, weighed and its position in the 13/sup 1///sub 2/ in. long fuel column recorded. Most of the pellets were centerless ground to a predetermined size. Four pins--two of each size--contained pellets that were sintered to size. The fuel density and O/M of the 0.230 in. OD pins were 90.75% TD and 1.96, respectively. The 0.250 in. OD pins contained fuel with a density of 92.40% and an O/M of 1.97. This test was conducted to verify that no fuel melting will occur in the FTR at 115% of the 400 MW rating.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- DOE Contract Number:
- EY-76-C-14-2170
- OSTI ID:
- 6786498
- Report Number(s):
- HEDL-SA-464; CONF-7411116-2
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
BREEDER REACTORS
CHALCOGENIDES
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FUEL ELEMENT FAILURE
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MELTING
OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
POWER DENSITY
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SIMULATION
SODIUM COOLED REACTORS
TEST REACTORS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
BREEDER REACTORS
CHALCOGENIDES
EBR-2 REACTOR
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FFTF REACTOR
FUEL ELEMENT FAILURE
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MELTING
OXIDES
OXYGEN COMPOUNDS
PHASE TRANSFORMATIONS
PLUTONIUM COMPOUNDS
PLUTONIUM DIOXIDE
PLUTONIUM OXIDES
POWER DENSITY
POWER REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SIMULATION
SODIUM COOLED REACTORS
TEST REACTORS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES