Fuel/cladding chemical interaction correlation for mixed-oxide fuel pins

Conference · Wed Jan 01 04:00:00 EST 1986 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:6907538

Lawrence, L A

A correlation was developed relating the depth of fuel/cladding chemical interaction (FCCI) to fabrication and operating parameters for uranium-plutonium oxide fuel pins with 20% cold-worked Type 316 stainless steel cladding. The data base for the FCCI correlation included all the Hanford Engineering Laboratory reference oxide fuel pins irradiated in experimental Breeder Reactor-II. Previous FCCI correlations were based on smaller numbers of fuel pins primarily from the high cladding temperature P-23 series. The expanded data base includes 305 data sets from 104 fuel pins with peak fuel burnups to 17.2 at.% and peak cladding inner surface temperatures to 730/sup 0/C. The increase in numbers of data sets as well as the broader range of applicability of the parameters in the revised wastage correlation provides greater assurance that predictions represent expected behavior.

• Research Organization: Westinghouse Hanford, Richland, WA
• OSTI ID: 6907538
• Report Number(s): CONF-861102-
• Conference Information: Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 53
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300* -- Nuclear Reactor Technology-- Fuel Elements
BURNUP
FABRICATION
FUEL ELEMENTS
FUEL PINS
FUEL-CLADDING INTERACTIONS
FUELS
HANFORD ENGINEERING DEVELOPMENT LABORATORY
IRRADIATION
MIXED OXIDE FUELS
NATIONAL ORGANIZATIONS
PERFORMANCE
REACTOR COMPONENTS
SOLID FUELS
TIME DEPENDENCE
US DOE
US ORGANIZATIONS