Simple computational model for the prediction of fuel pin failure during a transient-overpower accident. [LMFBR]
Thesis/Dissertation
·
OSTI ID:5416229
A fuel pin failure model is developed and incorported into a fast-running computer program. The model is designed to predict irradiated fuel-pin cladding rupture during a hypothetical transient-overpower (TOP) accident in a liquid metal fast breeder reactor. The principal failure mechanisms of fuel-cladding differential thermal expansion and fission-gas pressurization are accounted for. The prediction of cladding failure is based on a mechanistic calculation of the time-dependent cladding temperature and stress. A finite-difference thermal solution is used to obtain the radial temperature distribution in the pin. The pin mechanics calculation uses a very efficient few-fuel-node/single-cladding-node algorithm that utilizes the Tresca yield criterion to determine the onset of cladding plastic deformation. Comparisons are made between model predictions and the results of a number of Transient Reactor Test Facility TOP experiments. The importance of accurately modeling the fuel radial and circumferential crack characterization is investigated and discussed. The effect of model limitations is discussed and recommendations for future work are made.
- Research Organization:
- Illinois Univ., Urbana (USA)
- OSTI ID:
- 5416229
- 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
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CALCULATIONS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TRANSIENT OVERPOWER ACCIDENTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BREEDER REACTORS
COMPUTER CALCULATIONS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATHEMATICAL MODELS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
TRANSIENT OVERPOWER ACCIDENTS