Radiation-induced temperature shift of thhe ASME K/sub Ic/ curve

Conference · Sat Dec 31 23:00:00 EST 1988

OSTI ID:5974243

Nanstad, R K; Haggag, F M; Iskander, S K

The objective of this study was to determine the effects of neutron irradiation on the temperature shift and shape of the K/sub Ic/ curve described in Sect. XI of the ASME Boiler and pressure Vessel Code. Two submerged-arc welds with copper contents of 0.23 and 0.31 wt % were commercially fabricated in 215-mm-thick plate. Charpy impact, tensile, dropweight, and compact specimens up to 203.2 mm thick were fabricated and tested to provide a large data for unirradiated material. Similar specimens with compacts up to 101.6 mm thick, irradiated at about 288/degree/C to a mean fluence of about 1.6 /times/ 10/sup 19/ neutrons/cm/sup 2/ in the Oak Ridge Research Reactor, were tested to provide a similarly large data base with which to evaluate the temperature shift and shape of the ASME K/sub Ic/ curves. Testing was performed by both Oak Ridge National Laboratory and Materials Engineering Associates. Both linear-elastic and elastic-plastic fracture mechanics techniques were used to analyze test results. 3 refs., 4 figs., 1 tab.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5974243
• Report Number(s): CONF-890855-32; ON: DE89012344
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360106* -- Metals & Alloys-- Radiation Effects
ALLOYS
ARC WELDING
COPPER ALLOYS
DUCTILITY
FABRICATION
FRACTURE PROPERTIES
IRRADIATION
JOINING
JOINTS
MECHANICAL PROPERTIES
NEUTRON FLUENCE
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
REACTORS
SUBMERGED ARC WELDING
TENSILE PROPERTIES
WATER COOLED REACTORS
WELDED JOINTS
WELDING