Ex-reactor deformation of externally pressurized short lengths of fuel rod cladding. LWBR development program

Technical Report · Tue May 01 04:00:00 EDT 1979

DOI:https://doi.org/10.2172/6008533· OSTI ID:6008533

Selsley, I. A.

The DECAG (Deformation of Cladding into Axial Gaps) ex-reactor test program evaluated deformation of Zircaloy-4 cladding into axial gaps in tubular fuel elements. These axial gaps are the result of cladding elongation and fuel stack shrinkage. The test program consisted of twelve series and subseries of both fully recrystallized and stress-relieved highly cold worked tubing tested under pressure-temperature combinations in autoclaves. The test program also verified the validity of achieving test acceleration through the use of elevated temperatures by correlating both ovality and diameter change at lower temperatures with the Larson--Miller Parameter.

• Research Organization: Bettis Atomic Power Lab., West Mifflin, PA (USA)
• DOE Contract Number: EY-76-C-11-0014
• OSTI ID: 6008533
• Report Number(s): WAPD-TM-1404
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
ALLOYS
BREEDER REACTORS
DEFORMATION
FUEL CANS
LWBR TYPE REACTORS
PERFORMANCE TESTING
PRESSURE DEPENDENCE
REACTORS
TEMPERATURE DEPENDENCE
TESTING
THERMAL REACTORS
TIN ALLOYS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCALOY
ZIRCALOY 4
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS