Mechanisms behind irradiation-assisted stress corrosion cracking

Was, Gary S.; Andresen, Peter L.

doi:10.1016/b978-0-12-823719-9.00003-2

Cited by 10 publications

(6 citation statements)

References 88 publications

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“…2 For over 60 years, irradiation has played an increasingly important role in accelerating corrosion and in irradiation-assisted stress corrosion cracking (IASCC). [3][4][5] As plants age, the most important corrosion issues will center around stress corrosion cracking and the role of irradiation in both IASCC and corrosion.…”

Section: Write a Guest Blog Postmentioning

confidence: 99%

Corrosion in Advanced Nuclear Reactors

Was

Allen

2021

Electrochem. Soc. Interface

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Commercial nuclear power plants in the United States are light water reactors (LWRs) that use water as a coolant, with temperatures ranging between 280°C and 320°C. Water purity is tightly controlled; nevertheless, the high temperatures expose components in the water circuit to degradation by corrosion by many different types of environmental attack. Uniform corrosion occurs across the entire surface of a material and is prevalent in engineering systems to some extent. Site-specific corrosion processes, such as crevice corrosion, intergranular attack, or galvanic corrosion, are common in complex engineering systems that consist of multiple materials joined by welds or other solid state joining processes. Even within a single component, if second phase strengthening is used or if surface defects are present, localized corrosion can occur.

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Section: Write a Guest Blog Postmentioning

confidence: 99%

Corrosion in Advanced Nuclear Reactors

Was

Allen

2021

Electrochem. Soc. Interface

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“…Nuclear reactor power plant (NPP) internal components experience material property changes during service operation due to a complex interaction of several material degradation phenomena [1,2,3,4,5]. This degradation includes changes in the material microstructure and microchemistry under irradiated conditions, which can ultimately lead to intergranular irradiation assisted stress corrosion cracking (IASCC) [6,7,8,9,10]. The prime example of IASCC is the cracking of baffle to former bolts (BFBs), which has been observed for the first time in 1989 in French NPPs.…”

Section: Introductionmentioning

confidence: 99%

“…Though, as operating with irradiated materials is both difficult and expensive, little microscopical studies on neutron-irradiated cracks have been presented so far [17,18,19,20,21]. The emerging picture from available observations does suggest that intergranular oxide penetration enhances the cracking susceptibility under tensile stress [10], a factor which is strongly tied to the localized deformation close to the crack tip [22,23]. Lozano-Perez et al [24] showed that fast-diffusion paths, for instance along microstructural defects such as deformation bands and heavily dislocated structures, accelerate the oxidation process that may embrittle the boundary setting up to the requirements for cracking.…”

Section: Introductionmentioning

confidence: 99%

Microstructural investigation of IASCC crack tips extracted from thimble tube O-ring specimens

Penders¹,

Konstantinović²,

Yang³

et al. 2022

Journal of Nuclear Materials

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“…Despite for their desirable strength, fracture toughness, and general resistance to corrosion, austenitic stainless steels used for structural materials in nuclear power plants (NPPs) experience property changes as a consequence of complex material degradation phenomena [1,2,3,4,5]. These changes can bring about intergranular component failures in the form of irradiation-assisted stress corrosion cracking (IASCC) [6,7,8,9,10]. Prime examples of IASCC cracking entail the sudden intergranular failures of baffle-to-former bolts [11], first observed in French pressurized-water reactors (PWR).…”

Section: Introductionmentioning

confidence: 99%