Oxygen effects on irradiated tantalum alloys

Hosemann, Peter; Maloy, S.A.; Greco, Richard R.; Swadener, J.G.; Romero, Tobias J.

doi:10.1016/j.jnucmat.2008.09.027

Cited by 15 publications

(7 citation statements)

References 15 publications

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“…Previous studies have found that oxygen levels above 500 w ppm are sufficient to severely embrittle tantalum [16]. The increase from 1.9 GPa to 3.5 GPa in nanohardness measured in the tantalum bulk of the TaW-1 test article agrees roughly with the values determined by Hosemann et al for tantalum containing 400 w ppm oxygen measured using identical techniques [17]. This hardness was measured uniformly through the tantalum cladding thickness and repeated on multiple samples sectioned from various points on the TaW-1 target.…”

Section: Characterization Of Taw-1 Surface Phenomena and Bulk Responsesupporting

confidence: 85%

Fabrication of a tantalum-clad tungsten target for LANSCE

Nelson¹,

O’Toole²,

Valicenti³

et al. 2012

Journal of Nuclear Materials

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Section: Characterization Of Taw-1 Surface Phenomena and Bulk Responsesupporting

confidence: 85%

Fabrication of a tantalum-clad tungsten target for LANSCE

Nelson¹,

O’Toole²,

Valicenti³

et al. 2012

Journal of Nuclear Materials

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“…The room temperature samples were mounted the same way as described above for the 3.5 MeV alpha beam experiment and in the literature [10].…”

Section: Kev Proton Irradiation At Different Temperatures (Room Tmentioning

confidence: 99%

“…The tilt increases the analyzing area by a factor of 2-5 depending on the tilt angle and therefore increases the hardness vs. depth resolution significantly compared to previous work [7]. The polishing provided a very flat and smooth surface as required for nanoindentation [7,10]. The nanoindenter used was a Hysitron Triboindenter Ò instrument equipped with a multi range nanoprobe, an optical microscope and an atomic force microscope (AFM).…”

Section: Nanoindentation Atomic Force Microscopy and Transmission Elmentioning

confidence: 99%

Nanoindentation on ion irradiated steels

Hosemann

Vieh

Greco

et al. 2009

Journal of Nuclear Materials

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“…The sample mounting and irradiation were made the same way as described in [8]. The sample mounting and irradiation were made the same way as described in [8].…”

Section: Fine But Not Homogeniousmentioning

confidence: 99%

“…The sample mounting and irradiation were made the same way as described in [8]. After irradiation, all samples were analyzed using nanoindentation as described in [8,9]. The average beam current was between 600 nA and 750 nA depending on the irradiation experiment.…”

Section: Fine But Not Homogeniousmentioning

confidence: 99%

Nanostructured Engineering Alloys for Nuclear Application

et al. 2011

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In advanced nuclear applications, high temperature and a corrosive environment are present in addition to a high dose radiation field causing displacement damage in the material. In recent times it has been shown that Nanostructured Ferritic Alloys (NFA's) such as advanced Oxide Dispersion Strengthened (ODS) steels are suitable for this environment as they tolerate high dose irradiation without significant changes in microstructure or relevant mechanical properties. Ion beam irradiation is a fast and cost effective way to induce radiation damage in materials but has limited penetration depth. Therefore, small scale mechanical testing such as nanoindentation and micro compression testing in combination with FIB based sample preparation for micro structural characterization has to be performed allowing a full assessment of the materials' behavior under radiation environment. In this work two different ODS materials have been irradiated using proton and combined proton and He beams up to 1 dpa at different temperatures. Nanoindentation and LEAP measurements were performed in order to assess the changes in properties of these alloys due to irradiation. The same techniques were applied to intermetallic nanostructured alloys in order to investigate the effectiveness of the metal-intermetallic interface to provide defect sinks for He and radiation damage. It was found that irradiation can cause the formation of intermetallic particles even at room temperature while increasing the material strength significantly. 92

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Oxygen effects on irradiated tantalum alloys

Cited by 15 publications

References 15 publications

Fabrication of a tantalum-clad tungsten target for LANSCE

Fabrication of a tantalum-clad tungsten target for LANSCE

Nanoindentation on ion irradiated steels

Nanostructured Engineering Alloys for Nuclear Application

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