Intergranular Stress Corrosion Cracking of Unsensitized Stainless Steels in BWR Environments

Angeliu, Thomas M.; Andresen, Peter L.; Hall, Ernest L.; Sutliff, J. A.; Sitzman, Scott D.; Horn, R.M.

doi:10.1002/9781118787618.ch31

Cited by 39 publications

(14 citation statements)

References 5 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…More importantly, weld residual strains exist (along with weld residual stresses) in the heat affected zone of weld, and the equivalent room temperature tensile strain is often in the range of 20 % and sometimes as high as 30 % . Unsurprisingly, most SCC in stainless steels occurs in the heat affected zone near the weld fusion line, where the residual strain is highest (Andresen, 2010b;Angeliu et al, 1999Angeliu et al, , 2000.…”

Section: Effect Of Cold Workmentioning

confidence: 96%

“…SCC in the BWR core shroud occurs almost exclusively near circumferential and vertical welds, and initiation is observed from both the inside (ID) and outside (OD) surfaces (the shroud separates the upward core fl ow from the downward recirculation fl ow that occurs in the annulus between the shroud and the pressure vessel). This large diameter welded " pipe " has little active ( ∆ P) loading, and its susceptibility arises primarily from weld residual stresses and weld shrinkage strains (Angeliu, Andresen, Sutliff, & Horn, 1999;Angeliu et al, 2000;Othon & Morra, 2008). Cracking is observed in both low fl uence and moderate fl uence areas, and the extent of the enhancement in SCC susceptibility by irradiation is limited because, while radiation hardening and RIS occur, radiation creep also relaxes the weld residual stress.…”

Section: Plant Data On Iasccmentioning

confidence: 97%

See 1 more Smart Citation

Irradiation-assisted stress corrosion cracking

Was¹,

Ashida²,

Andresen³

2011

Corrosion Reviews

View full text Add to dashboard Cite

Irradiation-assisted stress corrosion cracking (IASCC) refers to the process(es) by which irradiation enhances the inherent susceptibility of alloys to stress corrosion cracking (SCC). This article begins with an introduction to the IASCC problem experienced in light water reactors, followed by a summary of existing plant and laboratory data that reveal its dependence on irradiation, environment and alloy parameters. The specifi c effects of irradiation on IASCC are classifi ed into two categories: the effects on water chemistry and the effects on microstructure. Water chemistry effects include radiolysis and its effects on corrosion potential, and effects of corrosion potential on IASCC. Microstructure effects include radiationinduced segregation (RIS), irradiated microstructure, swelling and creep, and hydrogen and helium generation. Leading mechanisms proposed to explain the role of radiation in the SCC process are: radiolysis and crack tip strain rate, grain boundary chromium depletion, irradiation hardening, localized deformation and RIS of minor elements. As nuclear power plants operate for longer, an increased incidence of SCC can be expected unless active mitigation steps are taken. Drawing on the accumulated understanding over the past four decades of the key processes believed to control IASCC, a set of attributes of an ideal, IASCC-resistant alloy are identifi ed as a fi rst step.

show abstract

Section: Effect Of Cold Workmentioning

confidence: 96%

Section: Plant Data On Iasccmentioning

confidence: 97%

Irradiation-assisted stress corrosion cracking

Was¹,

Ashida²,

Andresen³

2011

Corrosion Reviews

View full text Add to dashboard Cite

show abstract

“…Formation of Cr-rich carbides along grain boundaries may drastically deplete free chromium content in the area adjacent to the grain boundaries and render them susceptible to rapid preferential dissolution. Sensitized steels are most susceptible; the stress corrosion cracking of nonsensitized steels is also observed [14,15]. Dissolution of grain boundaries in some corrosive environments aside from tensile stress led these types of materials to SCC.…”

Section: Stainless Steelsmentioning

confidence: 99%

Stress Corrosion Cracking Damages

Khalifeh¹

2019

Failure Analysis

View full text Add to dashboard Cite

Stress corrosion cracking (SCC) is the formation and growth of crack through materials subjected to tensile stress and a specific corrosive medium. It can lead to unexpected sudden failure of normally ductile metals. Metal-environment combinations susceptible to cracking are specific. This means that all environments do not cause SCC on all of the alloys. Additionally, the environments that cause this kind of cracking have little corrosion effect on the alloy in normal conditions. In certain states, unwanted environmental and metallurgical changes have occurred and provide the metal-environment combination sensitive to SCC. The SCC sites on the metal surfaces may not be visible by visual inspection, while metal parts are being filled with microscopic cracks. These invisible cracks progress rapidly and lead the component and structures to catastrophic failures. In this chapter, the incidence of SCC on important industrial alloys from the chemical, metallurgical, and mechanical point of view is discussed.

show abstract

“…[1][2][3][4][5][6] SCC occurred in heat affected zones (HAZs) and also in weld metals. The majority of cracks stayed in the HAZs of diameter 600 mm PLR pipes, and in some cases, cracks grew into the weld metal regions.…”

Section: Introductionmentioning

confidence: 99%

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

Shoji

Takeda

2014

Corrosion Engineering, Science and Technology

View full text Add to dashboard Cite

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.

show abstract

Intergranular Stress Corrosion Cracking of Unsensitized Stainless Steels in BWR Environments

Cited by 39 publications

References 5 publications

Irradiation-assisted stress corrosion cracking

Irradiation-assisted stress corrosion cracking

Stress Corrosion Cracking Damages

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

Contact Info

Product

Resources

About