scholarly journals Stress corrosion cracking initiation and short crack growth behaviour in Alloy 182 weld metal under simulated boiling water reactor hydrogen water chemistry conditions

2018 ◽  
Vol 131 ◽  
pp. 208-222 ◽  
Author(s):  
Juxing Bai ◽  
Stefan Ritter ◽  
Hans-Peter Seifert ◽  
Sannakaisa Virtanen
Keyword(s):  
Weld Metal ◽  
Water Chemistry ◽  
Stress Corrosion ◽  
Crack Growth ◽  
Stress Corrosion Cracking ◽  
Boiling Water ◽  
Growth Behaviour ◽  
Crack Growth Behaviour ◽  
Water Reactor ◽  
Hydrogen Water

Disposition Curves for Irradiation-Assisted Stress Corrosion Cracking of Austenitic Stainless Steels in Light Water Reactor Environments

2015 ◽  
Author(s):  
Ernest D. Eason ◽  
Raj Pathania
Keyword(s):  
Water Chemistry ◽  
Stress Corrosion ◽  
Stress Corrosion Cracking ◽  
Laboratory Data ◽  
Austenitic Stainless Steels ◽  
Corrosion Cracking ◽  
Calibration Data ◽  
Pressurized Water ◽  
Water Reactor ◽  
Hydrogen Water

This paper presents irradiation-assisted stress corrosion cracking (IASCC) disposition curves developed in a multi-year international data collection, data review and modeling project. More than 800 IASCC crack growth rate (CGR) data points were collected from six laboratories worldwide, and an international panel of experts reviewed and ranked the data. The better-ranked data were used to calibrate empirical models for IASCC CGR in boiling water reactor (BWR) normal water chemistry (NWC) and hydrogen water chemistry (HWC) environments and in pressurized water reactor (PWR) primary water environments. The mean models were shifted upward to the 75th percentile of the calibration data for use as crack disposition curves. The disposition curves are presented in this paper and compared with data used for fitting and data not used for fitting, including field data from BWR core shrouds and additional laboratory data. The paper is intended as a basis document for possibly incorporating the new disposition curves in the ASME code.

Weld Residual Stresses and Primary Water Stress Corrosion Cracking in Bimetal Nuclear Pipe Welds

2007 ◽  
Author(s):  
Frederick W. Brust ◽  
Paul M. Scott
Keyword(s):  
Water Stress ◽  
Residual Stresses ◽  
Weld Metal ◽  
Stress Corrosion ◽  
Crack Growth ◽  
Stress Corrosion Cracking ◽  
Pressure Vessel ◽  
Large Diameter ◽  
Corrosion Cracking ◽  
Primary Water

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.

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