BWR pipe crack and weld clad overlay studies

Conference · Mon Oct 01 04:00:00 EDT 1984

OSTI ID:5999482

Shack, W J; Kassner, T F; Maiya, P S; Park, J Y; Ruther, W E

Leaks and cracks in the heat-affected zones of weldments in austenitic stainless steel piping in boiling water reactors (BWRs) due to intergranular stress corrosion cracking (IGSCC) have been observed since the mid-1960s. Since that time, cracking has continued to occur, and indication have been found in all parts of the recirculation system, including the largest diameter lines. Proposed solutions for the problem include procedures that produce a more favorable residual stress state on the inner surface, materials that are more resistant to stress corrosion cracking (SCC), and changes in the reactor environment that decrease the susceptibility to cracking. In addition to the evaluation of these remedies, it is also important to gain a better understanding of the weld overlay procedure, which is the most widely used short-term repair for flawed piping.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 5999482
• Report Number(s): CONF-8410142-72; ON: TI85004067
• 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
ALLOYS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
CRACKS
FABRICATION
GRAPHS
HEAT AFFECTED ZONE
IRON ALLOYS
IRON BASE ALLOYS
JOINING
JOINTS
PIPES
REACTORS
STAINLESS STEELS
STEELS
STRESS ANALYSIS
STRESS CORROSION
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
WELDING
ZONES