Effects of Material Composition on Corrosion Fatigue Crack Growth of Austenitic Stainless Steels in High Temperature Water

Platts, Norman; Tice, David; Mottershead, Kevin; McIntyre, Laura; Scenini, Fabio

doi:10.1002/9781118456835.ch58

Cited by 4 publications

(2 citation statements)

References 8 publications

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“…Evidence was also reported on the effect of oxidation on crack tip fields. Retardation of corrosion fatigue crack growth rates of austenitic stainless steels by high flow rate was reported by Platts et al, 31,32 which was associated with heavily oxidised bands on the fracture surface. Additional evidence is necessary for the contribution of DO on crack tip mechanics.…”

Section: Effects Of Do Concentration On Scc Growth Ratesmentioning

confidence: 83%

Effects of water chemistry on stress corrosion cracking of 316NG weld metals in high temperature water

Shoji

Takeda

2014

Corrosion Engineering, Science and Technology

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Effects of dissolved oxygen concentration from 0?2 to 11 ppm on stress corrosion cracking growth rates of 316NG weld metals in pure water at 288uC were investigated. Crack growth rates in the weld metal with a ferrite content of about 6?5 wt-% are higher than those in the weld metal with a ferrite content of about 8?5 wt-% under the same test environments, which increased with increasing dissolved oxygen concentration from 0?2 to 2 ppm. The dependence of crack growth rates on dissolved oxygen concentration in the range from 2 to 11 ppm was affected by the ferrite content in the weld metals.

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Section: Effects Of Do Concentration On Scc Growth Ratesmentioning

confidence: 83%

Effects of water chemistry on stress corrosion cracking of 316NG weld metals in high temperature water

Shoji

Takeda

2014

Corrosion Engineering, Science and Technology

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“…Such 'retarded' growth data are ignored in Mills' analysis and ASME Code Case N-809. Retardation is observed to be promoted by higher temperatures, high water flow rate, Figure 24(a) [58] and high sulphur content in the steel, Figure 24(b) [66]. Studies aimed at understanding the mechanisms influencing enhancement and retardation for the stainless steel/high-temperature water system indicate that it may be difficult to take benefit from retardation effects under circumstances in which sulphur depletion from the crack enclave can occur during long hold periods during plant operation.…”

Section: Austenitic Stainless Steelsmentioning

confidence: 99%

Contribution of research to the understanding and mitigation of environmentally assisted cracking in structural components of light water reactors

Tice

2017

Corrosion Engineering, Science and Technology

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Environmentally assisted cracking (EAC) is a potential threat to the safety and integrity of water-wetted components in operating water-cooled nuclear power plants. Two forms of EAC are commonly distinguished, depending on the form of loading contributing to damage: stress corrosion cracking (SCC) and corrosion fatigue. A number of instances of in-service degradation due to EAC have occurred in operating plants worldwide, often leading to unplanned plant outages. Understanding the causes of EAC is essential to minimise the loss of plant availability due to its occurrence and to avoid the possibility of catastrophic failure, for example, if a crack grew to a critical size in a major pressure boundary component. This paper will describe some examples of these phenomena in the main materials of construction of pressure boundary and other critical components in pressurised and boiling water reactors (BWRs). Over the last several decades, substantial research programmes have been carried out in a number of laboratories worldwide, aimed at further understanding of the processes leading to EAC to manage occurrences in plant and minimise future failures. Selected areas of research on EAC in light water reactor environments are discussed. Corrosion fatigue in low-alloy pressure vessel steels was the subject of considerable attention in the 1980s and early 1990s because of its potential threat to pressure vessel integrity and the publication of data, suggesting that there is a major influence of environment on fatigue crack growth in some laboratory tests. The author's research provided insight into the conditions under which the major environmental effects occur and contributed to the development of an ASME Code Case for pressurised water reactor (PWR) conditions which provided a means of screening based on steel sulphur content and loading conditions. More recently, the research focus in this area has moved to austenitic stainless steels, again providing support to Code Case development and furthering mechanistic understanding. A recent review of knowledge gaps for EPRI provides a basis for future research on environmentally assisted fatigue and will inform the development of new assessment methodologies. A key area of the current study concerns differences in loading conditions between specimens in laboratory tests and plant components subject to transient loading. In the case of SCC, stainless steels have shown the greatest propensity to cracking in BWRs, while Alloy 600 has been a major cause of in-service failures in PWRs, both on the primary side, as recognised by Coriou in the early 1960s, and in secondary environments where a number of different corrosionrelated failure processes have been identified. High-strength alloys, such as Alloy X-750 used for fastener applications, have also caused failures in both reactor types. For austenitic materials, SCC susceptibility is enhanced by irradiation, resulting in failures in core internals components. Ferritic stainless steels also undergo SCC under some specific circums...

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Mechanistic Understanding of Environmentally Assisted Fatigue Crack Growth of Austenitic Stainless Steels in PWR Environments

Medway¹,

Tice²,

Platts³

et al. 2017

The Minerals, Metals &Amp; Materials Series

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Effects of Material Composition on Corrosion Fatigue Crack Growth of Austenitic Stainless Steels in High Temperature Water

Cited by 4 publications

References 8 publications

Effects of water chemistry on stress corrosion cracking of 316NG weld metals in high temperature water

Effects of water chemistry on stress corrosion cracking of 316NG weld metals in high temperature water

Contribution of research to the understanding and mitigation of environmentally assisted cracking in structural components of light water reactors

Mechanistic Understanding of Environmentally Assisted Fatigue Crack Growth of Austenitic Stainless Steels in PWR Environments

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