There have been incidents recently where cracking has been observed in the bi-metallic welds that join the hot leg to the reactor pressure vessel nozzle. The hot leg pipes are typically large diameter, thick wall pipes. Typically, an inconel weld metal is used to join the ferritic pressure vessel steel to the stainless steel pipe. The cracking, mainly confined to the inconel weld metal, is caused by corrosion mechanisms. Tensile weld residual stresses, in addition to service loads, contribute to PWSCC (Primary Water Stress Corrosion Cracking) crack growth. In addition to the large diameter hot leg pipe, cracking in other piping components of different sizes has been observed. For instance, surge lines and spray line cracking has been observed that has been attributed to this degradation mechanism. Here we present some models which are used to predict the PWSCC behavior in nuclear piping. This includes weld model solutions of bimetal pipe welds along with an example calculation of PWSCC crack growth in a hot leg. Risk based considerations are also discussed.
Skip Nav Destination
ASME 2007 Pressure Vessels and Piping Conference
July 22–26, 2007
San Antonio, Texas, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
0-7918-4284-3
PROCEEDINGS PAPER
Weld Residual Stresses and Primary Water Stress Corrosion Cracking in Bimetal Nuclear Pipe Welds
Frederick W. Brust,
Frederick W. Brust
Battelle Memorial Institute, Columbus, OH
Search for other works by this author on:
Paul M. Scott
Paul M. Scott
Battelle Memorial Institute, Columbus, OH
Search for other works by this author on:
Frederick W. Brust
Battelle Memorial Institute, Columbus, OH
Paul M. Scott
Battelle Memorial Institute, Columbus, OH
Paper No:
PVP2007-26297, pp. 883-897; 15 pages
Published Online:
August 20, 2009
Citation
Brust, FW, & Scott, PM. "Weld Residual Stresses and Primary Water Stress Corrosion Cracking in Bimetal Nuclear Pipe Welds." Proceedings of the ASME 2007 Pressure Vessels and Piping Conference. Volume 6: Materials and Fabrication. San Antonio, Texas, USA. July 22–26, 2007. pp. 883-897. ASME. https://doi.org/10.1115/PVP2007-26297
Download citation file:
25
Views
Related Proceedings Papers
Related Articles
Improvement of Residual Stresses of Circumferential Joint of Pipe by Heat-Sink Welding
J. Pressure Vessel Technol (February,1986)
Experimental Study on Crack Growth Behavior for Austenitic Stainless Steel in High Temperature Pure Water
J. Pressure Vessel Technol (May,1986)
Welding Residual Stress Solutions for Dissimilar Metal Surge Line Nozzle Welds
J. Pressure Vessel Technol (April,2010)
Related Chapters
Development of Nuclear Boiler and Pressure Vessels in Taiwan
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition
Introduction and Definitions
Handbook on Stiffness & Damping in Mechanical Design
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards