Stress Corrosion Cracking of Alloy 52/152 Weldments Near Dissimilar Metal Weld Interfaces

2017 ◽  
pp. 67-85
Author(s):  
B. Alexandreanu ◽  
Y. Chen ◽  
W. -Y. Chen ◽  
K. Natesan
Keyword(s):  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
Dissimilar Metal ◽  
Dissimilar Metal Weld ◽  
Metal Weld

Stress Corrosion Cracking of the Fusion Boundary for 304L/82 Dissimilar Metal Weld Joint in Simulated Primary Water

CORROSION ◽  
10.5006/3343 ◽  
2019 ◽  
Vol 76 (2) ◽  
pp. 176-187
Author(s):  
Liang Zhao ◽  
Jiamei Wang ◽  
Haozhan Su ◽  
Donghai Du ◽  
Lefu Zhang ◽  
...  
Keyword(s):  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Heat Affected Zone ◽  
Corrosion Cracking ◽  
Intergranular Cracking ◽  
Fusion Boundary ◽  
Dissimilar Metal ◽  
Primary Water ◽  
Dissimilar Metal Weld ◽  
Metal Weld

The stress corrosion cracking behavior of the fusion boundary for 304L/82 dissimilar metal weld joint was studied in simulated primary water. Analytical electron microscopy was utilized to characterize the cracking features. Results demonstrated that the heat-affected zone in Type 304L has a higher stress corrosion cracking susceptibility and the crack propagated from weld region to Type 304L heat-affected zone in the form of intergranular cracking. The electron back-scattered diffraction and transmission electron microscopy–electron dispersive x-ray spectroscopy results showed that the intergranular cracking in the heat-affected zone of Type 304L was caused by the high residual strain rather than grain boundary Cr-depletion in front of the crack tip. The suppressed crack growth rate in hydrogenated water was attributed to the stable Cr-rich oxide formed at crack tip.

An Analytical Evaluation of the Full Structural Weld Overlay as a Stress Improving Mitigation Strategy to Prevent Primary Water Stress Corrosion Cracking in Pressurized Water Reactor Piping

2009 ◽  
Author(s):  
L. F. Fredette ◽  
Paul M. Scott ◽  
F. W. Brust ◽  
A. Csontos
Keyword(s):  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
Pressurized Water ◽  
Weld Overlay ◽  
Dissimilar Metal ◽  
Before And After ◽  
Primary Water ◽  
Water Reactors ◽  
Metal Weld

Full Structural Weld Overlay (FSWOL) has been used successfully to mitigate intergranular stress corrosion cracking in boiling water reactor (BWR) welded stainless steel piping for many years. The FSWOL technique adds structural reinforcement, can add crack resistant material, and can create compressive residual stresses at the inside surface of the welded joint which reduces the possibility of further stress corrosion cracking. Recently, the FSWOL has been applied as a preemptive measure to prevent primary water stress corrosion cracking (PWSCC) in pressurized water reactors (PWR) on susceptible welded pipes with dissimilar metal welds common to PWR primary cooling piping. This study uses finite element models to evaluate the likely residual and operating stress profiles remaining after FSWOL for typical dissimilar metal weld configurations, some of which are approved for leak-before-break (LBB) applications in pressurized water reactors. Circumferential cracks were modeled in the dissimilar metal weld area and forced to grow in order to evaluate their crack opening displacements and stress intensity factors vs. depth before and after weld overlay and before and after application of operating pressure and temperature.

An Analytical Evaluation of the Effect of Weld Material Thickness on Residual Stresses Produced by Structural Weld Overlays on Pressurized Water Reactor Primary Cooling Piping

2009 ◽  
Author(s):  
L. F. Fredette ◽  
Paul M. Scott ◽  
F. W. Brust ◽  
A. Csontos
Keyword(s):  
Residual Stresses ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Corrosion Cracking ◽  
Intergranular Stress Corrosion ◽  
Pressurized Water ◽  
Weld Overlay ◽  
Water Reactor ◽  
Dissimilar Metal ◽  
Structural Reinforcement

Full Structural Weld Overlay (FSWOL) has been used successfully to mitigate intergranular stress corrosion cracking in boiling water reactor (BWR) welded stainless steel piping for many years. The FSWOL technique adds structural reinforcement, can add crack resistant material, and can create compressive residual stresses at the inside surface of the welded joint which reduces the possibility of further stress corrosion cracking. Recently, the FSWOL has been applied as a preemptive measure to prevent primary water stress corrosion cracking (PWSCC) in pressurized water reactors (PWR) on susceptible welded pipes with dissimilar metal welds common to PWR primary cooling piping. This study uses finite element models to evaluate the likely residual and operating stress profiles remaining after FSWOL and describes the results of sensitivity studies which were performed to examine the effect of weld overlay thickness on the residual stresses for typical dissimilar metal weld configurations.

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