Precursor Evolution and Stress Corrosion Cracking Initiation of Cold-Worked Alloy 690 in Simulated Pressurized Water Reactor Primary Water

Zhai, Ziqing; Toloczko, Mychailo B.; Kruska, Karen; Bruemmer, S.M.

doi:10.5006/2470

Cited by 34 publications

(13 citation statements)

References 12 publications

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“…Then, the IG crack opens and slightly extends, and its flanks oxidize. Next, the mature crack continues to grow, in a way similar to creep [61]. Other microscopic investigation has shown that, initially, a compact layer of Cr 2 O 3 forms over a migrated GB (driven by the diffusion of Cr) and small cavities appear on the GB [62].…”

Section: Description Of Eac In the Corrosion Systemmentioning

confidence: 95%

“…Because the crack growth rate in the water was determined to be ten times higher than in the air, it has been suggested that the rate of cavity formation in Ni-based alloys, exposed to HT water, is also affected by penetrated hydrogen [23,30]; yet, this impact of hydrogen can be expected to be more pronounced for carbon steel. Another testing of EAC initiation with Alloy 690 exposed to simulated PWR primary water was interrupted at different stages of the initiation process in order to perform microscopical investigation [60][61][62][63], see Figure 8. It was found that with increasing time of exposure under load, fine cavities coalesce at GBs under the surface and form a microcrack.…”

Section: Description Of Eac In the Corrosion Systemmentioning

confidence: 99%

“…Another testing of EAC initiation with Alloy 690 exposed to simulated PWR primary water was interrupted at different stages of the initiation process in order to perform microscopical investigation [60][61][62][63], see Figure 8. It was found that with increasing time of exposure under load, fine cavities coalesce at GBs under the surface and form a microcrack.…”

Section: Description Of Eac In the Corrosion Systemmentioning

confidence: 99%

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Environmentally Assisted Cracking Initiation in High-Temperature Water

Hojná

2021

Metals

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Environmentally assisted cracking (EAC) is a very complex process that develops in materials that involve combining actions of environment and tensile loading. Crack initiation is the least explored stage and is not clearly defined. For this paper, current knowledge of crack initiation mechanisms was reviewed for three types of commercial structure materials exposed to high-temperature (HT) water coolants of power plants, namely ferritic low-alloy (LAS) and carbon (CS) steels, austenitic stainless (AS) steels, and nickel-based alloys. Physicochemical microprocesses engaged in the two earliest phases of the mechanism, the precursor and the incubation phases, are rather specific for each of these materials. In the latter, the slow growth phase, the crack development process passes into a sequence of repeating steps where the specific key microprocesses persist.

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Section: Description Of Eac In the Corrosion Systemmentioning

confidence: 95%

Section: Description Of Eac In the Corrosion Systemmentioning

confidence: 99%

Section: Description Of Eac In the Corrosion Systemmentioning

confidence: 99%

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Environmentally Assisted Cracking Initiation in High-Temperature Water

Hojná

2021

Metals

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“…Alloy 690TT has no corrosion issues reported to date while alloy 800NG has a larger in-service experience. SCC submodes may appear after long incubation periods and accelerated laboratory tests have shown alloy 690TT may suffer SCC, especially in the cold-work condition (Moss et al 2018;Zhai et al 2017). Therefore, immunity of alloy 690TT to the various SCC submodes cannot be claimed.…”

Section: Flow-assisted Corrosion Pipingmentioning

confidence: 99%

Corrosion control of nuclear steam generators under normal operation and plant-outage conditions: a review

Rodríguez

2020

Corrosion Reviews

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AbstractNuclear steam generators (NSGs) are key components of nuclear power plants (NPPs) since their reliability affects the overall plant performance. Corrosion control of steam generators under operation and during plant outages is attained by proper design, adequate material selection and control of water chemistry in the entire secondary cooling circuit. This article reviews the types of steam generators, the materials used for their construction (with a special focus on tubing alloys), the corrosion processes that may occur under operation and the strategies to preserve steam generators and other components of the secondary cooling system from corrosion during plant outages.

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“…In response to the serious impact of IGSCC in Alloy 600, Alloy 690 was designed to better resist IGSCC by increasing the Cr content to ~30 wt.%. As such, Alloy 690 has replaced Alloy 600 in many manufactured components such as steam generator tubes, control rod drive mechanism nozzles, and pressurizer heater sleeves in PWR [6][7][8][9][10][11] . To date, no incidence of IGSCC of Alloy 690 has been reported in PWRs in service in either primary or secondary circuits since its first use in the late 1980s.…”

Section: Introductionmentioning

confidence: 99%