Axial location of cladding failure during a slow transient overpower TREAT test. [LMFBR]
Conference
·
OSTI ID:6079369
The axial location of cladding failure following a transient overpower accident is of importance in fast reactor safety studies in that it is a determining factor in the relocation of fuel, and therefore in the possibility of inherent neutronic shutdown of the reactor. In-pile experimental data on the axial location of cladding failure of fuel in bundles of pins is sparse since, in general, the experimental fuel pin bundles are largely destroyed during the in-pile test. The post-test examination work has been completed for TREAT test J1. It was found that damage to the fuel elements during the irradiation was low enough for an accurate observation of the location of cladding failure to be made for each of the seven pins.
- Research Organization:
- Argonne National Lab., Idaho Falls, ID (USA)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 6079369
- Report Number(s):
- CONF-830609-67; ON: DE85004823
- Country of Publication:
- United States
- Language:
- English
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OSTI ID:6133551
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
AIR COOLED REACTORS
BREEDER REACTORS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SOLID HOMOGENEOUS REACTORS
STRESSES
TEST FACILITIES
TEST REACTORS
THERMAL REACTORS
THERMAL STRESSES
TRANSIENT OVERPOWER ACCIDENTS
TREAT REACTOR
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AIR COOLED REACTORS
BREEDER REACTORS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SOLID HOMOGENEOUS REACTORS
STRESSES
TEST FACILITIES
TEST REACTORS
THERMAL REACTORS
THERMAL STRESSES
TRANSIENT OVERPOWER ACCIDENTS
TREAT REACTOR