Residual-stress distributions near stainless steel butt weldments. [BWR]

Conference · Sun Jan 01 04:00:00 EST 1978

OSTI ID:6714480

Elligson, W. A.; Shack, W. J.

Concern for the integrity of stainless steel butt-weldments in boiling-water-reactor (BWR) piping systems has stimulated study of the conditions that cause stress corrosion cracking (SCC) in the heat-affected zones (HAZ) of the weldments. It is generally agreed that a high stress exceeding the initial yield strength is one of the essential elements for crack initiation. Since design procedures usually ensure that load stresses are below initial yield, the source of the high stresses necessary to produce SCC is thought to be the residual stresses due to welding. To examine the level of residual stresses in the weldments of interest, bulk residual stresses were measured on 100 mm (4-in.) and 254 mm (10-in.) diameter Schedule 80 piping weldments using strain relief techniques. Both laboratory welded specimens and field welded specimens from reactors in service were studied. Axial bulk residual stress distributions were obtained at 45/sup 0/ intervals around the circumference. At each azimuthal position, the residual stresses were measured at seven axial positions: on the weld centerline and 13, 20, and 25 mm on either side of the weld centerline on both the inside and outside surfaces.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: USDOE
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6714480
• Report Number(s): CONF-780565-2
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
BWR TYPE REACTORS
CHEMICAL REACTIONS
COOLING SYSTEMS
CORROSION
HEAT AFFECTED ZONE
JOINTS
PIPES
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RESIDUAL STRESSES
STRESS CORROSION
STRESSES
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS