Accelerated test for evaluation of intergranular stress corrosion cracking initiation characteristics of non-sensitized 316 austenitic stainless steel in simulated pressure water reactor environment

Zhong, Xiangyu; Bali, Shirish Chandrakant; Shoji, Tetsuo

doi:10.1016/j.corsci.2016.11.019

Cited by 54 publications

(13 citation statements)

References 67 publications

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“…Nevertheless, in the present study, Shim, Takeda and Shoji, Mechanical Engineering Journal, Vol.4, No.4 (2017) [DOI: 10.1299/mej.17-00035] the average crack distributions for the four cross sections under a given condition was employed. Figure 8 compares the average number of cracks and crack depths determined in the present study with the corresponding results of the SSRT tests conducted in simulated PWR primary water by Zhong et al (2016). The material and PWR environmental conditions of the two studies were the same.…”

Section: Crack Depth Distributions At Different Cross Sectionsmentioning

confidence: 95%

“…In addition, Zhong et al reported a second small peak within 200 μm in Fig. 8(a) (Zhong et al 2016), attributed to a hardened layer on the inner surface of the specimen produced by the drilling and honing process used for its preparation. Crack propagation was reportedly retarded by the hardened layer, with the growth of many cracks terminated within 100-200 μm.…”

Section: Crack Depth Distributions At Different Cross Sectionsmentioning

confidence: 99%

“…The CGR data obtained in a previous SSRT test conducted on the same material using a low strain rate of 2×10 -8 s -1 (Zhong et al, 2016) 10 -11 10 -10 10 -9 10 -8 10 -7 10 -6 10 -5 10 -4 10 [Zhong et al] max. CGR (2×10 -8 ) [Zhong et al] Strain rate strain amplitude 0.4% 0.6% 10 -2 %/s Shim, Takeda and Shoji, Mechanical Engineering Journal, Vol.4, No.4 (2017) [DOI: 10.1299/mej.…”

Section: (B) (A)mentioning

confidence: 99%

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Fatigue life prediction of 316 stainless steel in simulated PWR primary water by time domain analysis based on short fatigue crack growth behavior

Shim

Takeda

Shoji

2017

Mechanical Engineering Journal

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Fatigue life prediction of 316 stainless steel in simulated PWR primary water by time domain analysis based on short fatigue crack growth behavior AbstractThe fatigue life of austenitic stainless steel is significantly reduced in the environment of a pressurized water reactor (PWR). One of the methods for evaluating the environmental effect involves the use of the environmental correction factor (Fen) determined from the fatigue lives of the material in air and the PWR environment. It has been reported that the environmental correction factor increases with decreasing strain rate, eventually saturating at a low strain rate. However, the exact behavior of the parameter remains unclear considering evidences of a relationship between environmentally assisted fatigue and stress corrosion cracking. It is therefore of importance to examine the possibility of continuity between environmentally assisted fatigue and stress corrosion cracking at very low strain rates. In the present study, time domain analyses of short fatigue cracks initiated in 316 stainless steel in air and simulated PWR water were used to ascertain the existence of such continuity by investigating the relationship between the environmentally assisted fatigue and stress corrosion cracking. The acquired environmentally assisted fatigue life data were uniquely interpreted, and superposition of the plots of the stress corrosion cracking data obtained by slow-strain-rate tensile tests over the time domain analyses and environmentally assisted fatigue data suggested continuity among the parameters. This was clearly substantiated by further time domain analyses.Key words : Short fatigue crack growth behavior, Time domain analysis, Crack initiation, Simulated PWR primary water, Environmentally assisted fatigue, Stress corrosion cracking IntroductionEnvironmentally assisted fatigue (EAF) of structural materials exposed to high temperature, including in the primary water of a pressurized water reactor (PWR), has been studied over the past 30 years. The subject has attracted increased attention in more recent years owing to ongoing efforts toward the long-term operation (LTO) of nuclear power plants for up to 60 years. It is therefore necessary to investigate the safety and structural integrity issues of the long-term operation of a nuclear power plant field, especially regarding the primary coolant system components.Austenitic stainless steel, which is one of the most important structural materials, is utilized in primary pressure boundary components, where it is subjected to low-cycle fatigue (LCF) by repeated start-ups and shut-downs. Since the 1990s, there have been reports about the significance of a PWR environment to reduce the fatigue life of austenitic stainless steel.Both crack initiation and the propagation of a short crack have been investigated through crack initiation tests, with particular interest in the growth behavior of short fatigue cracks. Some fatigue life data are available in the Japan Nuclear Energy Safety Organization (JNES) report and ...

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Section: Crack Depth Distributions At Different Cross Sectionsmentioning

confidence: 95%

Section: Crack Depth Distributions At Different Cross Sectionsmentioning

confidence: 99%

Section: (B) (A)mentioning

confidence: 99%

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Fatigue life prediction of 316 stainless steel in simulated PWR primary water by time domain analysis based on short fatigue crack growth behavior

Shim

Takeda

Shoji

2017

Mechanical Engineering Journal

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“…SSRT testing is an accelerated approach for evaluating SCC susceptibility and serve as a screening test for assessing long‐term service performance of materials in different environments . Whenever there is lower stress corrosion crack velocity, slower initial strain rate should be selected to promote cracking .…”

Section: Introductionmentioning

confidence: 99%

“…Whenever there is lower stress corrosion crack velocity, slower initial strain rate should be selected to promote cracking . A strain rate of 10 −7 s −1 has been used by Zhong et al and Sáez‐Maderuelo et al in their experiments for evaluating SCC behavior in stainless steel. Novotny et al have pointed the fact that percentage of SCC fracture decreases as strain rate increases.…”

Section: Introductionmentioning

confidence: 99%

Behavior and susceptibility to stress corrosion cracking of a nickel‐based alloy in superheated steam and supercritical water

Khan

Zhang

Zhu

et al. 2018

Materials & Corrosion

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Stress corrosion cracking (SCC) behavior of Alloy 617 was studied to evaluate its suitability for Generation IV supercritical water reactor concept. A series of slow strain rate tensile (SSRT) tests at a constant strain rate of 5 × 10−7 s−1 were carried out in superheated steam and supercritical water over a pressure range of 0.1–25 MPa at 650 °C. SSRT test in dry N2 gas was also performed to compare the results in non‐corrosive environment with corrosive medium environment. Intergranular cracks were observed for all specimens regardless of the test environment. Alloy 617 showed susceptibility to SCC at the tested experimental conditions. The dominance of intergranular SCC was observed on the gage surface and fracture surface by using scanning electron microscope analysis. The effect of varying environmental conditions on SCC susceptibility is further discussed.

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Oxidation and SCC Initiation Studies of Type 304L SS in PWR Primary Water

Scenini¹,

Lindsay²,

Chang³

et al. 2017

The Minerals, Metals &Amp; Materials Series

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Slow strain rate tensile (SSRT) tests were conducted on conventional and tapered samples manufactured from forged Type 304L stainless steel to assess the stress corrosion cracking (SCC) behaviour in simulated PWR primary water. Several testing and microstructural parameters were investigated in order to explore the conditions under which crack initiation might occur. Surface preparation appeared to play a very important role on SCC initiation whereby the machined surfaces were the least susceptible to SCC initiation whilst oxide polishing suspension (OPS) polished surfaces were more susceptible. On the machined surfaces the cracks were always transgranular (TG) in nature and associated with the machining marks. Conversely, on fine polished surfaces with oxide polishing suspension the crack morphology was mainly intergranular in nature, although minor transgranular cracking was observed. The regions in the proximity of the ferrite/austenite interface were shown to be very susceptible to SCC initiation especially on the OPS polished surfaces and this was attributed to the strain localization upon dynamic deformation. Furthermore, intragranular inclusions appeared to dissolve and act as initiation sites for transgranular cracking to occur. The roles of strain rate, dynamic deformation and microstructure on the initiation of SCC are also discussed.

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Accelerated test for evaluation of intergranular stress corrosion cracking initiation characteristics of non-sensitized 316 austenitic stainless steel in simulated pressure water reactor environment

Cited by 54 publications

References 67 publications

Fatigue life prediction of 316 stainless steel in simulated PWR primary water by time domain analysis based on short fatigue crack growth behavior

Fatigue life prediction of 316 stainless steel in simulated PWR primary water by time domain analysis based on short fatigue crack growth behavior

Behavior and susceptibility to stress corrosion cracking of a nickel‐based alloy in superheated steam and supercritical water

Oxidation and SCC Initiation Studies of Type 304L SS in PWR Primary Water

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