Calibration of a fuel-to-cladding gap conductance model for fast reactor fuel pins

Technical Report · Mon May 01 00:00:00 EDT 1978

DOI:https://doi.org/10.2172/6863540· OSTI ID:6863540

Baker, R B

The report presents refined methods for calculation of fuel temperatures in PuO/sub 2/-UO/sub 2/ fuel in Fast Breeder Reactor (FBR) fuel pins. Of primary concern is the calculation of the temperature changes across the fuel-to-cladding gap of pins with fuel burnups that range from 60 to 10,900 MWd/MTM (0.006 to 1.12 at.%). Described in particular are: (1) a proposed set of heat transfer formulations and corresponding material properties for modeling radial heat transfer through the fuel and cladding; and (2) the calibration of a fuel-to-cladding gap conductance model, as part of a thermal performance computer code (SIEX-M1) which incorporates the proposed heat transfer expressions, using integral thermal performance data from two unique in-reactor experiments. The test data used are from the HEDL P-19 and P-20 experiments which were irradiated in the Experimental Breeder Reactor Number Two (EBR-II), for the Hanford Engineering Development Laboratory (HEDL).

• Research Organization: Hanford Engineering Development Lab., Richland, WA (United States)
• DOE Contract Number: EY-76-C-14-2170
• OSTI ID: 6863540
• Report Number(s): HEDL-TME-77-86
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FFTF REACTOR
FUEL PINS
CALIBRATION
HEAT TRANSFER
MATHEMATICAL MODELS
TEMPERATURE DISTRIBUTION
ENERGY TRANSFER
EPITHERMAL REACTORS
FAST REACTORS
FUEL ELEMENTS
LIQUID METAL COOLED REACTORS
REACTOR COMPONENTS
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220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors