Deuterium retention in V–4Cr–4Ti alloy after deuterium ion irradiation

Yamauchi, Yuji; Yamada, Tsuyoshi; Hirohata, Yuko; Hino, Tomoaki; Muroga, T.

doi:10.1016/j.jnucmat.2004.04.081

Cited by 16 publications

(10 citation statements)

References 15 publications

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“…It can be seen that carbon concentration was very high and was almost constant (~20~30 at.%) beyond the depth of ~10 nm for all samples. Similar results were observed in V-4Cr-4Ti alloy samples produced by GA [13] and NIFS-HEAT1 [12] by both AES and XPS analyses. Since Ar In the previous study, we found that after the heating at 673 K, no significant changes were observed in the surface of the sample 2, but, after the heating at 1473 K, a lot of blisters ruptured and a lot of pinholes was observed [6].…”

Section: Methodssupporting

confidence: 85%

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Helium thermal desorption and retention properties of V–4Cr–4Ti alloy used for first wall of breeding blanket

Hirohata

Yamada

Yamauchi

et al. 2006

Fusion Engineering and Design

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Helium irradiation experiments of V-4Cr-4Ti alloy with various surface treatments were conducted in an Electron Cyclotron Resonance (ECR) ion irradiation apparatus.After helium ion irradiation at room temperature, the helium thermal desorption and retention properties were examined by thermal desorption spectroscopy (TDS). Ion energy of helium beam was 5 keV. Three groups of desorption peaks appeared at around 500, 850 and 1200 K in the TDS spectrum. After helium ion irradiation at ion fluence of 1x10 21 He/m 2 , the retained helium desorbed mainly at around 1200 K and all of the implanted helium atoms were retained. With increasing fluence up to 5x10 21 He/m 2 , the amount of helium desorbed at 500 K increased. For the polished samples with annealing at various temperatures, the desorption peak observed at around 500 K shifted to higher temperature region. Smallest retained amount of helium was observed in the V-alloy with polishing followed by annealing at 1373 K.

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Section: Methodssupporting

confidence: 85%

“…vanadium and/or titanium carbides. In addition, it was also found that titanium was segregated in the near surface region (surface concentration of Ti was about 20 at.%) in the form of oxide [12]. Similar results were observed in both the sample 1 and 2 with annealing at 1373 K. The depth of the Ti-oxide layer was approximately 5 nm.…”

Section: Methodssupporting

confidence: 73%

Helium thermal desorption and retention properties of V–4Cr–4Ti alloy used for first wall of breeding blanket

Hirohata

Yamada

Yamauchi

et al. 2006

Fusion Engineering and Design

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“…The retained amount of deuterium diminished with increasing irradiation temperature because the release of implanted D atoms became large at 450 K [9] and the solubility of deuterium in the V-alloy decreased [15]. The q 773K values slightly increased with the gas fluence.…”

Section: Deuterium Retention Propertiesmentioning

confidence: 99%

Deuterium and helium retentions of V–4Cr–4Ti alloy used as first wall of breeding blanket in a fusion reactor

Hirohata

Yamada

Yamauchi

et al. 2006

Journal of Nuclear Materials

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The deuterium and helium retention properties of V-4Cr-4Ti alloy were investigated by thermal desorption spectroscopy (TDS). Ion energies of deuterium and helium were taken at 1.7 keV and 5 keV, respectively. The retained amount of deuterium in the sample irradiated at 380 K increased with the ion fluence and was not saturated to fluence of up to 1×10 23 D/m 2 . For the irradiation at 773 K, 0.1% of implanted deuterium was retained at the highest fluence. For the helium ion irradiation at room temperature, three groups of desorption peaks appeared at around 500, 850, and 1200 K in the TDS spectrum. In the lower fluence region (<1×10 21 He/m 2 ), the retained helium desorbed 2 mainly at around 1200 K. With increasing fluence, the amount desorbed at 500 K increased. Total amount of retained helium in the samples saturated at fluence up to 5×10 21 He/m 2 and saturation level was 2.7×10 21 He/m 2 .

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“…As with other materials, V can be damaged by radiation, and this will likely be the dominant trap in fusion reactors. [131,132] The recombination coefficient for H is over five orders of magnitude slower in V than in Ni in the range of operating temperatures, and is relatively insensitive to the surface concentration of sulfur [116]. Because of this and the high diffusivity of tritium, release is recombination-limited in V alloys.…”

Section: < Figure 15 Here>mentioning

confidence: 99%

Tritium Barriers and Tritium Diffusion in Fusion Reactors

Causey

Karnesky

Marchi

2012

Comprehensive Nuclear Materials

132

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Tritium and deuterium induce radiation in reactor materials and some radioactive tritium gas may be released. Most of the materials used in fusion reactors are metals that have relatively high permeabilities for tritium. The fusion community has been working on barriers to minimize tritium release. Unfortunately, most barrier materials work very well during laboratory experiments, but fail to meet requirements when placed in radiation environments.This chapter presents tritium permeation characteristics of various materials used in fusion reactors, including plasma-facing, structural, and barrier materials. The necessary parameters for tritium release calculations for various regions of a fusion reactor are given.

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Deuterium retention in V–4Cr–4Ti alloy after deuterium ion irradiation

Cited by 16 publications

References 15 publications

Helium thermal desorption and retention properties of V–4Cr–4Ti alloy used for first wall of breeding blanket

Helium thermal desorption and retention properties of V–4Cr–4Ti alloy used for first wall of breeding blanket

Deuterium and helium retentions of V–4Cr–4Ti alloy used as first wall of breeding blanket in a fusion reactor

Tritium Barriers and Tritium Diffusion in Fusion Reactors

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