With the recent occurrences of primary water stress corrosion cracking (PWSCC) at nickel-based dissimilar metal welds (specifically Alloy 82/182 welds) in the nation’s pressurized water reactors (PWRs), the commercial nuclear power industry has been proposing a number of mitigation strategies for dealing with the problem. Some of these methods include Mechanical Stress Improvement Process (MSIP), Full and Optimized Structural Weld Overlay (FSWOL, OWOL) and Inlay and Onlay welds. All of these methods provide either a reduction in the ID residual stress field, (MSIP and WOL) and/or apply a corrosion resistant layer to stop or retard a leak path from forming (WOL, Inlay, Onlay). For the larger bore pipe, i.e. hot leg outlet nozzle, methods such as FSWOL become cost prohibitive due to the amount of weld metal that must be deposited. Therefore, inlay welds are being proposed since only a small layer (3 weld beads) needs to be deposited on the inside surface of the pipe. Currently the ASME code is developing Code Case N-766 ‘Nickel Alloy Reactor Coolant Inlay and Cladding for Repair or Mitigation of PWR Full Penetration Circumferential Nickel Alloy Welds in Class 1 Items.’ This code case is documenting the procedures for applying these inlay welds. As part of a confirmatory analysis, the US NRC staff and its contractor, Engineering Mechanics Corporation of Columbus, (Emc2) have conducted both welding residual stress and flaw evaluation analyses to determine the effectiveness of inlay welds as a mitigative technique. This paper presents the ongoing results from this effort. Using several large bore geometries, detailed welding simulation analyses were conducted on the procedures set forth in draft Code Case N-766. Effects of weld repairs and temper bead welding are included. Using these residual stress results, PWSCC growth analyses were conducted using simulated crack growth rates as a function of chromium content to estimate the time to leakage and rupture for small initial flaws in the inlay. The paper concludes with discussions on the effectiveness of inlays based on these analyses.
Skip Nav Destination
ASME 2009 Pressure Vessels and Piping Conference
July 26–30, 2009
Prague, Czech Republic
Conference Sponsors:
- Pressure Vessels and Piping
ISBN:
978-0-7918-4369-7
PROCEEDINGS PAPER
Welding Residual Stress and Flaw Evaluation for Dissimilar Metal Welds With Alloy 52 Inlays
D. Rudland,
D. Rudland
U. S. Nuclear Regulatory Commission, Washington, DC
Search for other works by this author on:
A. Csontos,
A. Csontos
U. S. Nuclear Regulatory Commission, Washington, DC
Search for other works by this author on:
F. Brust,
F. Brust
Engineering Mechanics Corporation of Columbus, Columbus, OH
Search for other works by this author on:
T. Zhang
T. Zhang
Engineering Mechanics Corporation of Columbus, Columbus, OH
Search for other works by this author on:
D. Rudland
U. S. Nuclear Regulatory Commission, Washington, DC
A. Csontos
U. S. Nuclear Regulatory Commission, Washington, DC
F. Brust
Engineering Mechanics Corporation of Columbus, Columbus, OH
T. Zhang
Engineering Mechanics Corporation of Columbus, Columbus, OH
Paper No:
PVP2009-77167, pp. 319-326; 8 pages
Published Online:
July 9, 2010
Citation
Rudland, D, Csontos, A, Brust, F, & Zhang, T. "Welding Residual Stress and Flaw Evaluation for Dissimilar Metal Welds With Alloy 52 Inlays." Proceedings of the ASME 2009 Pressure Vessels and Piping Conference. Volume 6: Materials and Fabrication, Parts A and B. Prague, Czech Republic. July 26–30, 2009. pp. 319-326. ASME. https://doi.org/10.1115/PVP2009-77167
Download citation file:
17
Views
Related Proceedings Papers
Related Articles
Welding Residual Stress Solutions for Dissimilar Metal Surge Line Nozzle Welds
J. Pressure Vessel Technol (April,2010)
Observations on the Interaction of High Mean Stress and Type II Hot Corrosion on the Fatigue Behavior of a Nickel Base Superalloy
J. Eng. Gas Turbines Power (January,1985)
Residual Stress Measurement in 304 Stainless Steel Weld Overlay Pipes
J. Eng. Mater. Technol (January,1996)
Related Chapters
Iwe and Iwl
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Third Edition
IWE and IWL
Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 2, Second Edition: Criteria and Commentary on Select Aspects of the Boiler & Pressure Vessel and Piping Codes
Development of Nuclear Boiler and Pressure Vessels in Taiwan
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 3, Third Edition