Radiation-induced segregation and corrosion behavior on Σ3 coincidence site lattice and random grain boundaries in proton-irradiated type-316L austenitic stainless steel

Sakaguchi, Norihito; Endo, M.; Watanabe, Seiichi; Kinoshita, Hironori; Yamashita, Shinichiro; Kokawa, Hiroyuki

doi:10.1016/j.jnucmat.2012.11.036

Cited by 45 publications

(12 citation statements)

References 24 publications

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“…RIS has been successfully used to investigate the sink characteristics of specific grain boundary types in both austenitic and ferritic/martensitic steels using experiments and modeling [25][26][27][28][29][30][31][32][33][34][35][36]. These studies have shown the grain boundary type, whether a low-angle grain boundary, random high-angle grain boundary, or low-Σ coincident site lattice (CSL) boundary, will have different sink characteristics due to the local structure of the grain boundary and can be correlated to their coherency and hence grain boundary energetics.…”

Section: Numerous Light Water Reactor (Lwr) Nuclear Power Plants In Tmentioning

confidence: 99%

Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments

et al. 2015

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Radiation induced segregation (RIS) is a well-studied phenomena which occurs in many structurally relevant nuclear materials including austenitic stainless steels. RIS occurs due to solute atoms preferentially coupling with mobile point defect fluxes that migrate and interact with defect sinks. Here, a 304 stainless steel was neutron irradiated up to 47.1 dpa at 320°C. Investigations into the RIS response at specific grain boundary types were utilized to determine the sink characteristics of different boundary types as a function of irradiation dose. A rate theory model built on the foundation of the modified inverse Kirkendall (MIK) model is proposed and benchmarked to the experimental results. This model, termed the GiMIK model, includes alterations in the boundary conditions based on grain boundary structure and expressions for interstitial binding. This investigation, through experiment and modeling, found specific grain boundary structures exhibit unique defect sink characteristics depending on their local structure. Such interactions were found to be consistent across all doses investigated and to have larger global implications, including precipitation of Ni-Si clusters near different grain boundary types.

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Section: Numerous Light Water Reactor (Lwr) Nuclear Power Plants In Tmentioning

confidence: 99%

Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments

et al. 2015

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“…. Sakaguchi et al[140] have attempted to exploit this behavior by a grain-boundary engineering approach that attempts to incorporate large numbers of Σ3 boundaries.Modeling of the dependence of RIS on grain boundary character requires the introduction of a parameter that captures the strength of the boundary as a point-defect sink. Models that do this successfully have been developed by Duh et al[141] and Sakaguchi et al…”

mentioning

confidence: 99%

Radiation-induced solute segregation in metallic alloys

Ardell

Bellon

2016

Current Opinion in Solid State and Materials Science

113

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The subject of radiation-induced solute segregation (RIS) in metallic alloys is reviewed. RIS manifests itself in several different ways, including diffusion to point-defect sinks (dislocations, grain boundaries, voids, etc.), which can induce precipitation in undersaturated alloys, as well as self-organization of solute clusters and precipitation in defect-free material.Diffusion in dilute and concentrated alloys is highlighted, as are theories of RIS that include new ideas on diffusion of complexes involving coupling between fluxes of point defects and of solute atoms. Many important experimental observations are presented, including up-to-date findings using atom-probe tomography, with special emphasis on solute segregation in austenitic and ferritic steels. Results from computational modeling and theory are also presented and discussed in light of experimental findings. Examples illustrating the factors affecting RIS are shown and some important outstanding issues that impact the current understanding of RIS are described and discussed.

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“…Nevertheless, this is dependent on the nature of the grain boundary. Grain boundary type and nature are related to the RIS occurring and therefore so is their oxidation behaviour [38,39].…”

Section: Effect O F I Rradiation O N T He G Rain B Oundary Oxidationmentioning

confidence: 99%

Role of irradiation and irradiation defects on the oxidation first stages of a 316L austenitic stainless steel

et al. 2019

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The role of irradiation and irradiation defects on the oxidation first stages of 316 L alloy was investigated. A sample with both a proton pre-irradiated and an unirradiated area was exposed to a simulated PWR environment during 24 hours. Irradiation defects and Radiation Induced Segregation at grain boundary and on irradiation defects were characterized and quantified and their effect on the oxidation was evaluated. Irradiation affects the morphology, thickness and chemistry of the oxide layers formed. It enhances the oxidation kinetic and induces the formation of an inner oxide richer in chromium. Defects induced by irradiation act as preferential nucleation sites.

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Radiation-induced segregation and corrosion behavior on Σ3 coincidence site lattice and random grain boundaries in proton-irradiated type-316L austenitic stainless steel

Cited by 45 publications

References 24 publications

Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments

Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments

Radiation-induced solute segregation in metallic alloys

Role of irradiation and irradiation defects on the oxidation first stages of a 316L austenitic stainless steel

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