Residual Stress and Stress Corrosion Cracking of High Pressure Hydrocarbon Transmission Pipelines

Author(s):  
Greg Van Boven ◽  
Ronald Rogge ◽  
Weixing Chen

Stress corrosion cracking (SCC) can occur on the exterior surface of high pressure hydrocarbon transmission pipelines fabricated from low carbon steels. Both the initiation of SCC and the ability of SCC to progressively increase in depth is a complex and poorly understood phenomena. Previous empirical evidence suggests that residual stresses may be involved in this initiation and growth process. This paper describes a laboratory research project designed to investigate the correlation between residual stress and SCC. In this project, tensile test specimens with increasing levels of compressive and tensile residual stress on the surface and through the thickness of the specimen were fabricated. These stresses were sufficiently large as to dominate the other slight variations in material properties that may occur on identically formed test specimens. The residual stresses were then mapped across the length and through the depth of the specimens by a non-destructive neutron diffraction technique. A SCC initiation process was applied to the specimens. It was found that the formation of micro-pitting, to a depth up to 200 μm, occurred preferentially in areas where tensile residual stresses were the highest (about 300 MPa). Initiation of SCC, although found all at the bottom of this micro-pitting, occurred with a 71% normalized frequency in locations where the surface residual stress was in the range of 150 MPa to 200 MPa. Experimental data revealed that cracks generated in near-neutral pH environments can be readily blunted, due to both plastic deformation (room temperature creep) and extensive dissolution. As a result, a high positive tensile residual stress gradient is necessary for developing cracks in pipeline steels exposed to near-neutral pH environments. The tensile residual stress represents a large mechanical driving force for initial crack nucleation and short crack growth. Active cracks may become dormant as the near-surface residual stress gradient changes from a high to a low tensile stress or if the stress becomes compressive due to self-equilibration through the wall thickness direction. Special conditions may exist in pipeline steels where crack dormancy may not occur within a short distance to the surface, which may include, for example, the presence of a large tensile residual stress gradient over a longer distance, particular microstructures conducive to galvanic corrosion, and special environmental conditions susceptible to hydrogen-induced cracking.

Author(s):  
J. Broussard ◽  
P. Crooker

The US Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute (EPRI) are working cooperatively under a memorandum of understanding to validate welding residual stress predictions in pressurized water reactor primary cooling loop components containing dissimilar metal welds. These stresses are of interest as DM welds in pressurized water reactors are susceptible to primary water stress corrosion cracking (PWSCC) and tensile weld residual stresses are one of the primary drivers of this stress corrosion cracking mechanism. The NRC/EPRI weld residual stress (WRS) program currently consists of four phases, with each phase increasing in complexity from lab size specimens to component mock-ups and ex-plant material. This paper describes the Phase 1 program, which comprised an initial period of learning and research for both FEA methods and measurement techniques using simple welded specimens. The Phase 1 specimens include a number of plate and cylinder geometries, each designed to provide a controlled configuration for maximum repeatability of measurements and modeling. A spectrum of surface and through-wall residual stress measurement techniques have been explored using the Phase 1 specimens, including incremental hole drilling, ring-core, and x-ray diffraction for surface stresses and neutron diffraction, deep-hole drilling, and contour method for through-wall stresses. The measured residual stresses are compared to the predicted stress results from a number of researchers employing a variety of modeling techniques. Comparisons between the various measurement techniques and among the modeling results have allowed for greater insight into the impact of various parameters on predicted versus measured residual stress. This paper will also discuss the technical challenges and lessons learned as part of the DM weld materials residual stress measurements.


Author(s):  
Mark Wenman ◽  
James Barton ◽  
Kenneth Trethewey ◽  
Sean Jarman ◽  
Paul Chard-Tuckey

Austenitic stainless steels (ASS) have excellent resistance to general corrosion. However, these steels can be susceptible to localised corrosion such as pitting and crevice corrosion. In the presence of a tensile stress they can also exhibit stress corrosion cracking (SCC). In pressurised water reactor (PWR) nuclear plant incidents of SCC, especially chloride-induced SCC (CISCC), have been observed. Chloride ions which can lead to CiSCC of even low carbon austenitic grades can be introduced from many sources including the atmosphere and materials introduced into the reactor environment. Stress can result from primary loading or introduced as secondary stresses, such as residual stress, through machining or welding processes. Residual stresses are internal self-balancing stresses that can act alone or together with a primary stress to cause premature failure of a component. 15 mm lengths of 304L ASS tube were subjected to an in-plane compression of between 1–10 mm before unloading. This created regions of plasticity and on relaxation the specimen contains a complex state of residual stresses that can be modelled by finite element (FE) methods. The tube specimens were then boiled in MgCl2 for 14 days before metallographic examination. A FE model of transgranular CISCC has been created by writing a VUMAT user subroutine implemented into the commercial FE code ABAQUS. The model is based on simple rules which include the initiation of surface corrosion pits from which, under mechanical control, SCC cracks may propagate. The model includes rules for SCC growth, based on hydrostatic stress state, and can incorporate the idea of grain orientation effects. Cracks created interact with and modify the residual stress field in the tube. Test results were then compared with model outputs. Crack morphologies and to a certain extent crack positions matched well with experiment. Attempts were made to calculate the crack tip driving forces from the model. The results also highlight the need to consider the importance of triaxial stress states, created by pits and cracks, and stress as a tensor rather than a scalar property. The effect of grain misorientation is also investigated, but so far, found to be of more limited importance for modelling transgranular CISCC.


Author(s):  
Ashish Thakur

This paper analyzes stress corrosion cracking (SCC) of pre-cracked samples in the presence of compressive residual stresses generated in the vicinity of the crack tip during fatigue pre-cracking. Research focuses on the role of cracktip residual stresses of compressive nature, generated by fatigue loading, in stress corrosion cracking of pre-cracked samples of medium high strength aluminum alloy 7020 subjected to localized anodic dissolution and hydrogen assisted cracking. Fatigue pre-cracking load on the samples generates compressive residual stresses in the vicinity of the crack tip which improve the stress corrosion behavior of the aluminum alloy by delaying either the metal dissolution or the hydrogen entry, thus increasing the fracture load in an aggressive environment. The rice model of the residual stress distribution in the vicinity of a crack tip may be usedto explain these retardation effects by estimating the stress level and plastic zone size. Microscopically, compressive residual stress produce a transition topography between the fatigue pre-crack and the cleavage-like (unstable) fracture mode.


2004 ◽  
Vol 126 (4) ◽  
pp. 465-473 ◽  
Author(s):  
Adrian T. DeWald ◽  
Jon E. Rankin ◽  
Michael R. Hill ◽  
Matthew J. Lee ◽  
Hao-Lin Chen

This paper examines the effects of laser peening on Alloy 22 (UNS N06022), which is the proposed material for use as the outer layer on the spent-fuel nuclear waste canisters to be stored at Yucca Mountain. Stress corrosion cracking (SCC) is a primary concern in the design of these canisters because tensile residual stresses will be left behind by the closure weld. Alloy 22 is a nickel-based material that is particularly resistant to corrosion; however, there is a chance that stress corrosion cracking could develop given the right environmental conditions. Laser peening is an emerging surface treatment technology that has been identified as an effective tool for mitigating tensile redisual stresses in the storage canisters. The results of laser-peening experiments on Alloy 22 base material and a sample 33 mm thick double-V groove butt-weld made with gas tungsten arc welding (GTAW) are presented. Residual stress profiles were measured in Alloy 22 base material using the slitting method (also known as the crack-compliance method), and a full 2D map of longitudinal residual stress was measured in the sample welds using the contour method. Laser peening was found to produce compressive residual stress to a depth of 3.8 mm in 20 mm thick base material coupons. The depth of compressive residual stress was found to have a significant dependence on the number of peening layers and a slight dependence on the level of irradiance. Additionally, laser peening produced compressive residual stresses to a depth of 4.3 mm in the 33 mm thick weld at the center of the weld bead where high levels of tensile stress were initially present.


2013 ◽  
Vol 747-748 ◽  
pp. 723-732 ◽  
Author(s):  
Ru Xiong ◽  
Ying Jie Qiao ◽  
Gui Liang Liu

This discussion reviewed the occurrence of stress corrosion cracking (SCC) of alloys 182 and 82 weld metals in primary water (PWSCC) of pressurized water reactors (PWR) from both operating plants and laboratory experiments. Results from in-service experience showed that more than 340 Alloy 182/82 welds have sustained PWSCC. Most of these cases have been attributed to the presence of high residual stresses produced during the manufacture aside from the inherent tendency for Alloy 182/82 to sustain SCC. The affected welds were not subjected to a stress relief heat treatment with adjacent low alloy steel components. Results from laboratory studies indicated that time-to-cracking of Alloy 82 was a factor of 4 to 10 longer than that for Alloy 182. PWSCC depended strongly on the surface condition, surface residual stresses and surface cold work, which were consistent with the results of in-service failures. Improvements in the resistance of advanced weld metals, Alloys 152 and 52, to PWSCC were discussed.


Author(s):  
Frederick W. Brust ◽  
Paul M. Scott

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.


2021 ◽  
Vol 73 (07) ◽  
pp. 53-54
Author(s):  
Chris Carpenter

This article, written by JPT Technology Editor Chris Carpenter, contains highlights of paper NACE 2020-14695, “Comparison of Stress Corrosion Cracking Behavior of Fe13Cr5Ni- and Fe17Cr5.5Ni-Based High-Chromium Stainless Steels in High-Pressure/High-Temperature CO2 Environments,” by Yameng Qi, Zhonghua Zhang, and Chunxia Zhang, Baoshan Iron and Steel, prepared for the 2020 NACE International Corrosion Conference and Exposition, Houston, 14–18 June. The paper has not been peer reviewed. Stress corrosion cracking (SCC) of Fe13Cr5Ni- and Fe17Cr5.5Ni-based alloys in high-pressure/high-temperature (HP/HT) carbon dioxide (CO2) environments was investigated through slow-strain-rate tests (SSRTs) and electrochemical methods. The results show that a remarkable decrease in tensile strength and elongation to failure was observed when testing in a CO2 environment compared with that of air. Fe17Cr5.5Ni-based alloys possessed better SCC resistance than Fe13Cr5Ni-based alloys. The better SCC resistance of the former could be attributed to good repassivation capacity and pitting-corrosion resistance induced by the increase in chromium (Cr) and nickel (Ni) content. Introduction When service temperature exceeds 150°C, SCC resistance of Fe13Cr5Ni-based alloys could become an issue. Compared with Fe13Cr5Ni-based alloys, 22Cr duplex stainless steel has an excel-lent performance when exposed to temperatures over 150°C and stable SCC resistance in HP/HT CO2 environments. However, the cost of 22Cr duplex stainless steel is extremely high. Experimental Procedure Fe13Cr5Ni- and Fe17Cr5.5Ni-based alloys were produced by the authors’ research institute. The materials were in a quenched and tempered state. For micrographic observation, each specimen was ground with 2,000-grit carbide silicon paper and polished with 1.2-µm diamond paste. They were then degreased with acetone and etched with hydrochloric ferric chloride solution (a mixture of 5-g ferric chloride, 25-mL hydrochloric acid, and 25-mL ethanol). The steel microstructures were characterized using an optical micro-scope. The micrograph in Fig. 1a for the F-13Cr5Ni-based alloys shows a martensite phase with no notable second phases. Fe17Cr5.5Ni alloys possess long strip ferrite and martensite phases (Fig. 1b). For SSRTs, smooth tensile specimens with a gauge length of 25.4 mm and a diameter of 3.81 mm were prepared. The specimens were cut from the Fe13Cr5Ni- and Fe17Cr5.5Ni-based alloys into an 8-mm-thick, 12-mm-outer- diameter disc for electrochemical measurement. All specimens were polished to a 1,200-grit surface finish, degreased with acetone, cleansed with distilled water, and dried in air. SSRT and electrochemical-measurement procedures are detailed in the complete paper. Results SCC Susceptibility. As expected, tensile strength and elongation to failure of Fe13Cr5Ni- and Fe17Cr5.5Ni-based alloys deteriorated in HP/HT CO2 environments. Compared with an environment of air, the elongation to failure of Fe13Cr5Ni- and Fe17Cr5.5Ni-based alloys in HP/HT CO2 environments decreased by approximately 30 and 25%, respectively. In addition, tensile strength and elongation to failure of Fe17Cr5.5Ni-based alloys were greater than those of Fe13Cr5Ni-based alloys. Elongation, reduction in area, and time to failure of Fe17Cr5.5Ni-based alloys were found to be much higher than that of Fe13Cr5Ni-based alloys in HP/HT CO2 environments. It can be concluded that Fe17Cr5.5Ni alloys possess better SCC resistance than Fe13Cr5Ni alloys in these environments.


Author(s):  
Frederick W. Brust ◽  
R. E. Kurth ◽  
D. J. Shim ◽  
David Rudland

Risk based treatment of degradation and fracture in nuclear power plants has emerged as an important topic in recent years. One degradation mechanism of concern is stress corrosion cracking. Stress corrosion cracking is strongly driven by the weld residual stresses (WRS) which develop in nozzles and piping from the welding process. The weld residual stresses can have a large uncertainty associated with them. This uncertainty is caused by many sources including material property variations of base and welds metal, weld sequencing, weld repairs, weld process method, and heat inputs. Moreover, often mitigation procedures are used to correct a problem in an existing plant, which also leads to uncertainty in the WRS fields. The WRS fields are often input to probabilistic codes from weld modeling analyses. Thus another source of uncertainty is represented by the accuracy of the predictions compared with a limited set of measurements. Within the framework of a probabilistic degradation and fracture mechanics code these uncertainties must all be accounted for properly. Here we summarize several possibilities for properly accounting for the uncertainty inherent in the WRS fields. Several examples are shown which illustrate ranges where these treatments work well and ranges where improvement is needed. In addition, we propose a new method for consideration. This method consists of including the uncertainty sources within the WRS fields and tabulating them within tables which are then sampled during the probabilistic realization. Several variations of this process are also discussed. Several examples illustrating the procedures are presented.


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