Failure analysis of carbide fuels under transient overpower (TOP) conditions. [LMFBR]

Conference · Sun Jun 01 00:00:00 EDT 1980

OSTI ID:5046331

Nguyen, D. H.

The failure of carbide fuels in the Fast Test Reactor (FTR) under Transient Overpower (TOP) conditions has been examined. The Beginning-of-Cycle Four (BOC-4) all-oxide base case, at $.50/sec ramp rate was selected as the reference case. A coupling between the advanced fuel performance code UNCLE-T and HCDA Code MELT-IIIA was necessary for the analysis. UNCLE-T was used to determine cladding failure and fuel preconditioning which served as initial conditions for MELT-III calculations. MELT-IIIA determined the time of molten fuel ejection from fuel pin.

• Research Organization: Hanford Engineering Development Lab., Richland, WA (USA)
• DOE Contract Number: AC14-76FF02170
• OSTI ID: 5046331
• Report Number(s): HEDL-SA-2006-FP; CONF-800607-88; TRN: 80-017846
• Resource Relation: Conference: American Nuclear Society annual meeting, Las Vegas, NV, USA, 8 Jun 1980
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL ELEMENT FAILURE
LMFBR TYPE REACTORS
TRANSIENT OVERPOWER ACCIDENTS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
FFTF REACTOR
FUEL PINS
PLUTONIUM CARBIDES
REACTOR SAFETY
STAINLESS STEEL-316
TEMPERATURE GRADIENTS
URANIUM CARBIDES
ACCIDENTS
ACTINIDE COMPOUNDS
ALLOYS
BREEDER REACTORS
CARBIDES
CARBON COMPOUNDS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENTS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MATERIALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PLUTONIUM COMPOUNDS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SODIUM COOLED REACTORS
STAINLESS STEELS
STEELS
TEST REACTORS
TRANSURANIUM COMPOUNDS
URANIUM COMPOUNDS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors