Review of advances in development of vanadium alloys and MHD insulator coatings

Muroga, T.; Chen, J. M.; Чернов, В. М.; Fukumoto, Ken-ichi; Hoelzer, David T.; Kurtz, Richard J.; Nagasaka, Tetsuya; Pint, Bruce A.; Satou, Mamoru; Suzuki, Atsuyuki; Watanabe, Hideo

doi:10.1016/j.jnucmat.2007.03.082

Cited by 93 publications

(34 citation statements)

References 42 publications

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“…1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 55 56 57 58 59 60 61 62 63 64 65 3 Vanadium-based alloys currently constitute advanced candidate materials for the first wall of future fusion reactors such as DEMO [1,2]. In particular, V-4Cr-4Ti alloy offers an outstanding combination of high-temperature strength and radiation resistance [3][4][5], coupled with low neutron activation [6,7] and corrosion resistance to liquid metal coolants [8][9][10].…”

Section: ) Direct Comparison With the Results Of Neutron-irradiatiomentioning

confidence: 99%

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Monolayer-thick TiO precipitation in V-4Cr-4Ti alloy induced by proton irradiation

et al. 2017

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We have characterised to atomic resolution the mono-layer thick TiO-type precipitate induced by proton irradiation in V-4Cr-4Ti alloy at the coarsening radiation-induced interstitial a/2⟨111⟩ dislocation loops expected to exert a minimal effect on the precipitate formation. This monolayer-thick precipitate constitutes an early stage in the radiationinduced aging process of V-4Cr-4Ti at low temperatures, and can potentially absorb additional light elements in reactor environments. 1Moor Row, November 24, 2016 Dear Prof. Beyerlein, Please find attached the resubmitted manuscript SMM-16-1716 entitled 'Monolayer-thick TiO precipitation in V-4Cr-4Ti alloy induced by proton irradiation' which has been significantly revised on the basis of the comments received by the reviewers.The detailed response to the reviewers' comments, together with the revised version of the manuscript, is attached. We would like to thank the reviewers for their time and effort in appraising the manuscript. The comments received were pertinent and helpful in improving the manuscript. All the points raised have been addressed and the manuscript has been amended accordingly. We believe that the revisions made adequately address the points raised and should therefore present no further obstacle to publication. We thank the reviewers for carefully reading the manuscript and the useful comments. We have addressed all those comments, which we feel have improved the article's quality.Detailed response:1.) In figure 2, images for SA and SACW irradiated at 350C are necessary for better understanding of temperature effects. We have included additional text in the manuscript about the temperature effect. The novelty and impact of this work lies in the recovery of the CWed structure already at 300°C (Fig. 2) before the formation of monolayer-thick RIPs at 350°C (Fig. 3). 2.) What is the relationship between the observed microstructure and the hardness? For example, for SA irradiated at 300C and 350C, where does the difference in hardening come?We have added some text to clarify the observed hardening behaviour at different temperatures in terms of the observed microstructure. 3.) As the observed RIPs in this study is platelet, the description as "average size" may mislead.We have changed the average size of the monolayer-thick RIPs by their average length. 4.) The description about recovery of the pre-existing dislocation network in SACW is contradicting in page 6 and page 7.We have clarified the contradiction in page 6 and 7. 5.) Direct comparison with the results of neutron-irradiation might be difficult since the damage rate is exceedingly large.We have added some text about the difference in dose rate and particle fluence between neutron and proton irradiation. The formation and evolution of a/2 ⟨111⟩ unfaulted dislocation loops in our proton irradiated samples correspond to the observations reported in neutron-irradiated material. However the average loop size at 350C in the proton irradiated samples (85nm) is lower than the value repo...

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Section: ) Direct Comparison With the Results Of Neutron-irradiatiomentioning

confidence: 99%

“…In particular, V-4Cr-4Ti alloy offers an outstanding combination of high-temperature strength and radiation resistance [3][4][5], coupled with low neutron activation [6,7] and corrosion resistance to liquid metal coolants [8][9][10].…”

Section: Introductionmentioning

confidence: 99%

Monolayer-thick TiO precipitation in V-4Cr-4Ti alloy induced by proton irradiation

et al. 2017

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“…Er 2 O 3 electric insulating coating is being developed for reduction of the MHD pressure drop in Li/V-alloy blanket systems [1]. It was demonstrated that the Er 2 O 3 coating serves also as a tritium permeation barrier of blanket systems made of other breeder and coolant such as Flibe and Li-Pb [2].…”

Section: Inroductionmentioning

confidence: 99%

Ion-Beam Induced Luminescence and Damage of Er<sub>2</sub>O<sub>3</sub>

Kato

Sakaue

Murakami

et al. 2012

Plasma and Fusion Research

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Ion-beam induced luminescence of sintered Er 2 O 3 samples irradiated by Ar + ion-beams was measured in a visible range. In this experiment, three emission bands were observed at 500-520, 540-570, and 640-690 nm. The measured luminescence band at 640-690 nm is resolved into Lorentzian Stark component having a ∼ 10 12 Hz width in frequency. Center wavelengths of the Stark components agree with those of intra-4f transitions of Er 3+ (4f 11 ) ions situated at C 2 symmetry cation sites in pure Er 2 O 3 . However, resonance broadening due to nearby Er 3+ in the crystal accounts only 1% of the total width. Depopulation of the crystalline oxide in irradiated regions is inferred from decreasing intensity of the emission band at 640-690 nm during continuous irradiation. The emission bands at 500-520 and 540-570 nm still remained in heavily damaged samples look similar with those observed with a metallic Er target. InroductionEr 2 O 3 electric insulating coating is being developed for reduction of the MHD pressure drop in Li/V-alloy blanket systems [1]. It was demonstrated that the Er 2 O 3 coating serves also as a tritium permeation barrier of blanket systems made of other breeder and coolant such as Flibe and Li-Pb [2]. However, neutron damages of the coating in fusion reactors are a big concern. Ion-beam damages are often used to simulate the neutron damages. Changes in crystallinity of the irradiated sample may be inferred from changes in ion-beam induced luminescence spectra, because optical transitions of trivalent Er ions (Er 3+ ) in the Er 2 O 3 crystals are known rather strong and sharp [3]. The ground state of Er 3+ has an incomplete 4f sub-shell (4f 11 ). The intra-4f transitions from lower excited states to the ground state are observed as the luminescence in Infrared and visible ranges. Tanaka et al. [4] investigated the ion-beam induced visible luminescence of Er 2 O 3 coating samples irradiated by 100 keV H + and Ar + ion-beams at Osaka Univ. The similar measurements have recently been undertaken using an apparatus in NIFS in order to understand relations between the crystallinity and the luminescence spectra. In the present study, the visible spectra of sintered Er 2 O 3 samples bombarded by Ar + ion-beams were measured.author 's e-mail: kato.daiji@nifs.ac.jp * ) This article is based on the presentation at the 21st International Toki Conference (ITC21). Experimental Apparatus and MethodThe experimental apparatus consists of an ion-beam source, a collision chamber, and a CCD spectrometer. The ion source is a part of medium current ion implanter (UL-VAC IM-200MH-FB) used for semiconductor production (Freeman-type) in NIFS [5]. Ion-beam extracted from the Freeman ion source was introduced into the collision chamber after analyzing the mass to charge ratio by a magnet. We could use primary Ar + ion beam of about 0.1 ∼ 100 μA in current at 33, 50, and 70 keV in kinetic energy. In the collision chamber, target samples are set on a grounded movable stage made of stainless steels. The stage can be moved in d...

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“…The Er 2 O 3 coating has been investigated as insulator for liquid lithium blanket system [14,15]. Therefore there are limited data as TPB and the permeation mechanism through the coating has not been clarified yet.…”

Section: Introductionmentioning

confidence: 99%

Deuterium permeation behavior of erbium oxide coating on austenitic, ferritic, and ferritic/martensitic steels

Chikada

Suzuki

Yang

et al. 2009

Fusion Engineering and Design

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Tritium permeation barrier is required in fusion blanket for reduction of loss of fuel and health hazard. In this study, deuterium permeation experiments have been 2 performed on four kinds of steels and erbium oxide coatings fabricated by a filtered arc deposition method. The permeation flux of uncoated samples shows diffusion-limited regime in the temperature range 573−723 K and the permeability is corresponding to literature data. The coated samples deposited at room temperature have been tested at 773 K. It is found that the coatings suppress the deuterium permeation to a close level in spite of different types of steel substrates. In addition, the exponent of the driving pressure slightly changes compared to the uncoated sample. However, the permeation regime is still near diffusion limited.

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Review of advances in development of vanadium alloys and MHD insulator coatings

Cited by 93 publications

References 42 publications

Monolayer-thick TiO precipitation in V-4Cr-4Ti alloy induced by proton irradiation

Monolayer-thick TiO precipitation in V-4Cr-4Ti alloy induced by proton irradiation

Ion-Beam Induced Luminescence and Damage of Er<sub>2</sub>O<sub>3</sub>

Deuterium permeation behavior of erbium oxide coating on austenitic, ferritic, and ferritic/martensitic steels

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