Evaluating strength and ductility of irradiated Zircaloy. Task 5. Quarterly progress report, July--September 1976

Technical Report · Fri Oct 01 04:00:00 EDT 1976

OSTI ID:7334603

Bauer, A A; Lowry, L M; Perrin, J S

Tensile tests were performed on unirradiated Zircaloy tubing; the effect of temperature on these properties also was investigated. Burst test-data were obtained on specimens of irradiated H.B. Robinson fuel-rod cladding at temperatures ranging from 400 to 800/sup 0/F at a single circumferential strain rate and at 700/sup 0/F with varying strain rates. Uniform elongation shows no effect of either test temperature or strain rate, while failure strain increases and strength properties tend to decrease as temperature increases and strain rate decreases. Additional transient and isothermal anneals followed by axial tensile tests were performed. The data served to emphasize the strength maximum and ductility minimum, as measured by total elongation, that is observed as recovery of irradiated tubing is initiated, as well as the lag in ductility recovery behind that of strength as annealing proceeds. Tensile tests of stress-relieved, unirradiated Zircaloy tubing did not reveal a similar change in properties as annealing proceeded. Burst properties of transient and isothermally annealed irradiated fuel-rod cladding were measured. Differences in burst and tensile property response to annealing were evidenced in the ductility changes. In particular, the uniform elongation measured in the burst test first decreased and then increased as recovery proceeded whereas the tensile uniform elongation did not show a similar ductility minimum in the recovery process. 11 fig, 6 tables.

• Research Organization: Battelle Columbus Labs., OH (USA)
• OSTI ID: 7334603
• Report Number(s): BMI-NUREG-1961
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
ANNEALING
DUCTILITY
ELONGATION
FAILURES
FUEL CANS
HEAT TREATMENTS
MECHANICAL PROPERTIES
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STRAIN RATE
TEMPERATURE DEPENDENCE
TENSILE PROPERTIES
TIN ALLOYS
TUBES
ZIRCALOY
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS