In-pile MFCI test of carbide fuel, TREAT test AX1. [LMFBR]
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:6595306
None
- Research Organization:
- Argonne National Lab., IL
- OSTI ID:
- 6595306
- Report Number(s):
- CONF-800607-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 34
- Country of Publication:
- United States
- Language:
- English
Similar Records
Analysis of in-pile MFCI experiments with carbide fuel
Fuel failure sequence for TREAT test E7. [LMFBR]
Fuel motion in TREAT transient overpower test E8. [LMFBR]
Conference
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Thu Jun 01 00:00:00 EDT 1978
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:6862968
Fuel failure sequence for TREAT test E7. [LMFBR]
Conference
·
Tue Jun 01 00:00:00 EDT 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7264233
Fuel motion in TREAT transient overpower test E8. [LMFBR]
Conference
·
Sun Oct 31 23:00:00 EST 1976
· Trans. Am. Nucl. Soc.; (United States)
·
OSTI ID:7328696
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
AIR COOLED REACTORS
BREEDER REACTORS
CARBIDES
CARBON COMPOUNDS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL-COOLANT INTERACTIONS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
SOLID HOMOGENEOUS REACTORS
STRESSES
TEMPERATURE GRADIENTS
TEST REACTORS
THERMAL REACTORS
THERMAL STRESSES
TREAT REACTOR
URANIUM CARBIDES
URANIUM COMPOUNDS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
AIR COOLED REACTORS
BREEDER REACTORS
CARBIDES
CARBON COMPOUNDS
ENRICHED URANIUM REACTORS
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
FUEL-COOLANT INTERACTIONS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HOMOGENEOUS REACTORS
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
RESEARCH AND TEST REACTORS
SAFETY
SIMULATION
SOLID HOMOGENEOUS REACTORS
STRESSES
TEMPERATURE GRADIENTS
TEST REACTORS
THERMAL REACTORS
THERMAL STRESSES
TREAT REACTOR
URANIUM CARBIDES
URANIUM COMPOUNDS