Critique of ''LMFBR fuel pin cladding transient performance capabilities: an analysis of FCTT data,'' BNWL-2041, NRC-1
The report BNWL-2041 was prepared by Battelle-Northwest Laboratory for the U.S. Nuclear Regulatory Commission to aid in the assessment of the safety margin provided by the CRBRP transient performance design criteria. The report compares certain aspects of the fuel pin transient performance analysis in the CRBRP PSAR with experimental test results obtained with the Fuel Cladding Transient Tester (FCTT) on EBR-II irradiated fuel pin cladding. Failure temperature, residual strength, and failure strain values obtained by the FCTT are used in BNWL-2041 to question the CRBRP fuel pin design temperature limits for upset and emergency events, the residual strength values employed in the Cumulative Mechanical Damage Function (CDF), and the allowed incremental strain during upset and emergency events. This paper critically reviews the evaluations in BNWL-2041 to assure that FCTT results are correctly analyzed, interpreted, and applied.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA)
- Sponsoring Organization:
- US Energy Research and Development Administration (ERDA)
- DOE Contract Number:
- E(45-1)-2170
- OSTI ID:
- 7138399
- Report Number(s):
- HEDL--TC-672
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ACCIDENTS
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
LIQUID METAL COOLED REACTORS
NEUTRON FLUX
PERFORMANCE TESTING
POWER REACTORS
RADIATION FLUX
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SODIUM COOLED REACTORS
STRAINS
STRESSES
TEMPERATURE DEPENDENCE
TESTING
210500* -- Power Reactors
Breeding
ACCIDENTS
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FUEL CANS
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PINS
LIQUID METAL COOLED REACTORS
NEUTRON FLUX
PERFORMANCE TESTING
POWER REACTORS
RADIATION FLUX
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SODIUM COOLED REACTORS
STRAINS
STRESSES
TEMPERATURE DEPENDENCE
TESTING