PROPERTIES OF A HAFNIUM CONTROL ROD AFTER EXPOSURE DURING TWO SEED LIVES IN PWR CORE 1

Technical Report · Thu Nov 01 04:00:00 EST 1962

OSTI ID:4715825

Salvaggio, G J; Nichols, F A; Bacca, Jr, J P

S>A PWR cortrol rod irradiated to as high as 1 x 10/sup 22/ nvt ()0.625 ev) during two seed lives in the Shippingport Atomic Power Station was destructively tested in an effort to determine the effect of irradiation on the properties of Hf and to further assess the consequences of abnormal corrosion of the weld joints of Zircaloy-2 welded to Hf. Tests performed included hardness, tensile postirradiation corrosion, chemical analysis, and metallographic examinations. Results of these tests indicate that the strength increase follows a two-step process with an apparent saturation between 3.8 and 5.8 x 10/sup 21/ nvt and an additioral increase in strength at higher exposure, while the useful ductility decreases slightly. There are no apparent limitations of the cortrol rods to further use arising from the observed corrosion at the weld joint, and short-time corrosion tests have not uncovered an acceleration of corrosion caused by buildup of transmutation elements. It is concluded, therefore, that Hf is adequate for continued use in PWR. However, further trends in property changes should be established by additional testing after each succeeding refueling. (auth)

• Research Organization: Westinghouse Electric Corp. Bettis Atomic Power Lab., Pittsburgh
• DOE Contract Number: AT(11-1)-GEN-14
• NSA Number: NSA-17-010074
• OSTI ID: 4715825
• Report Number(s): WAPD-TM-337
• Country of Publication: United States
• Language: English

Related Subjects

BURNUP
CONTROL ELEMENTS
CORROSION
HAFNIUM
HARDNESS
IRRADIATION
JOINTS
MATERIALS TESTING
MECHANICAL PROPERTIES
METALLOGRAPHY
NEUTRON FLUX
POWER PLANTS
PRODUCTION
PWR
QUALITATIVE ANALYSIS
QUANTITATIVE ANALYSIS
RADIATION EFFECTS
RADIOISOTOPES
REACTOR CORE
REACTOR FUELING
REACTOR TECHNOLOGY
REACTORS
RODS
SHIPPINGPORT
TENSILE PROPERTIES
VELOCITY
WELDING
WELDS
ZIRCALOY