Repair welding of heavy-section steel components in LWRs. Volume 2. Detailed technical description of thw work. Research Project 1236-1. Final report
Technical Report
·
OSTI ID:6471694
An EPRI-sponsored program was carried out by Babcock and Wilcox to develop an alternative weld repair procedure to the half bead technique suitable for in-service repair of nuclear reactor pressure vessel components without subsequent post weld heat treatment. The new weld repair procedure uses conventional machining for defect excavation/cavity preparation and the cold wire gas tungsten-arc process as the weld method. A controlled heat input, multi-pass welding procedure produces excellent grain refinement and tempering of the base metal HAZ without the necessity for grinding the first layer. The cavity preparation and weld repair processes combined with the elimination of grinding gives a significant advantage to the implementation of this new repair procedure in a radioactive environment. A characterization of the mechanical properties for weldments representative of the half bead technique and the new alternate repair procedure included both conventional and fracture mechanics based testing. The data indicates that both repair procedures are capable of producing repair weldments having material properties adequate for service in nuclear pressure boundary components.
- Research Organization:
- Babcock and Wilcox Co., Alliance, OH (USA). Research and Development Div.
- OSTI ID:
- 6471694
- Report Number(s):
- EPRI-NP-3614-Vol.2; ON: TI84920513
- Country of Publication:
- United States
- Language:
- English
Similar Records
Repair welding of heavy-section steel components in LWRs. Volume 1. Summary report. Final report
Controlled, all-position, butterbead-temperbead welding technique for nuclear repairs
Performance of repair welds on service-aged 2-1/4Cr-1Mo girth weldments
Technical Report
·
Sun Jul 01 00:00:00 EDT 1984
·
OSTI ID:6648341
Controlled, all-position, butterbead-temperbead welding technique for nuclear repairs
Journal Article
·
Fri Jan 31 23:00:00 EST 1986
· Weld. J. (Miami); (United States)
·
OSTI ID:6052114
Performance of repair welds on service-aged 2-1/4Cr-1Mo girth weldments
Journal Article
·
Fri Oct 31 23:00:00 EST 1997
· Journal of Pressure Vessel Technology
·
OSTI ID:549417
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
CONTAINERS
FABRICATION
JOINING
JOINTS
NOZZLES
PRESSURE VESSELS
PWR TYPE REACTORS
QUALITY ASSURANCE
REACTORS
REPAIR
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
WELDING
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BWR TYPE REACTORS
CONTAINERS
FABRICATION
JOINING
JOINTS
NOZZLES
PRESSURE VESSELS
PWR TYPE REACTORS
QUALITY ASSURANCE
REACTORS
REPAIR
WATER COOLED REACTORS
WATER MODERATED REACTORS
WELDED JOINTS
WELDING