Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel

Field, Kevin G.; Barnard, Leland; Parish, Chad M.; Busby, Jeremy T.; Morgan, Dane; Allen, Todd R.

doi:10.1016/j.jnucmat.2012.12.026

Cited by 66 publications

(37 citation statements)

References 40 publications

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“…Key research includes studies on radiation damage phenomena including segregation under irradiation, radiation induced hardening in ceramics, clustering dynamics of irradiated oxide dispersion strengthened steels, nuclear fuel stability under irradiation, and surface analysis of relevant material systems [5][6][7][8][9][10][11][12][13][14][15]. Here, selected results from research conducted using the UW-IBL and CLIM are presented to demonstrate the facility's capabilities as well as selected research results.…”

Section: Resultsmentioning

confidence: 99%

University of Wisconsin Ion Beam Laboratory: A facility for irradiated materials and ion beam analysis

Field¹,

Wetteland²,

Cao³

et al. 2013

AIP Conference Proceedings

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Section: Resultsmentioning

confidence: 99%

University of Wisconsin Ion Beam Laboratory: A facility for irradiated materials and ion beam analysis

Field¹,

Wetteland²,

Cao³

et al. 2013

AIP Conference Proceedings

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“…Multiple studies have measured radiation induced segregation (RIS) in BCC Fe-Cr steels by collecting line scans using STEM-EDX. [5][6][7][8][9] This section will describe the methods contributing to a sound RIS measurement, including experimental setup, error analysis, and measurement limitations. Examples of STEM-EDX RIS measurements in BCC Fe-Cr steels will also be illustrated.…”

Section: Ris Measurementsmentioning

confidence: 99%

“…For F/M alloys, prior austenite grain boundaries (PAGBs) tend to be higher-angle boundaries and exhibit greater RIS than lower-angle boundaries or low-R coincident site grain boundaries. 7,14 Unfortunately, PAGBs are often difficult to align because of the carbide decoration, which exceeds 60% coverage of the PAGB in commercial BCC F/M steels. 8 This leaves only short grain boundary segments, often on the order of tens of nanometers, on which to conduct an alignment.…”

Section: Ris Measurementsmentioning

confidence: 99%

Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys

Parish

Field

Certain³

et al. 2015

J. Mater. Res.

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107

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This paper provides an overview of advanced scanning transmission electron microscopy (STEM) techniques used for characterization of irradiated BCC Fe-based alloys. Advanced STEM methods provide the high-resolution imaging and chemical analysis necessary to understand the irradiation response of BCC Fe-based alloys. The use of STEM with energy dispersive x-ray spectroscopy (EDX) for measurement of radiation-induced segregation (RIS) is described, with an illustrated example of RIS in proton-and self-ion irradiated T91. Aberration-corrected STEM-EDX for nanocluster/nanoparticle imaging and chemical analysis is also discussed, and examples are provided from ion-irradiated oxide dispersion strengthened (ODS) alloys. Finally, STEM techniques for void, cavity, and dislocation loop imaging are described, with examples from various BCC Fe-based alloys.

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“…The depletion of Cr might enhance irradiation-assisted stress corrosion cracking of SS, and this might reduce the integrity of nuclear power plants, especially in case of boiling water reactors [2][3]. Thus, numerous studies on RIS in SS and model alloys have been performed over the three last decades [4][5][6][7][8][9][10][11][12][13].…”

Section: Introductionmentioning

confidence: 99%

Atomistic Analysis Of Radiation-Induced Segregation In Ion-Irradiated Stainless Steel 316

Lee¹,

Jin²,

Chang³

et al. 2015

Archives of Metallurgy and Materials

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Stainless steel (SS) is a well-known material for the internal parts of nuclear power plants. It is known that these alloys exhibit radiation-induced segregation (RIS) at point defect sinks at moderate temperature, while in service. The RIS behavior of SS can be a potential problem by increasing the susceptibility to irradiation-assisted stress corrosion cracking. In this work, the RIS behavior of solute atoms at sinks in SS 316 irradiated with Fe 4+ ions were characterized by atom probe tomography (APT). There were torus-shaped defects along with a depletion of Cr and enrichment of Ni and Si. These clusters are believed to be dislocation loops resulting from irradiation. The segregation of solutes was also observed for various defect shapes. These observations are consistent with other APT results from the literature. The composition of the clusters was analyzed quantitatively almost at the atomic scale. Despite the limitations of the experiments, the APT analysis was well suited for discovering the structure of irradiation defects and performing a quantitative analysis of RIS in irradiated specimens.

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Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel

Cited by 66 publications

References 40 publications

University of Wisconsin Ion Beam Laboratory: A facility for irradiated materials and ion beam analysis

University of Wisconsin Ion Beam Laboratory: A facility for irradiated materials and ion beam analysis

Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys

Atomistic Analysis Of Radiation-Induced Segregation In Ion-Irradiated Stainless Steel 316

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