Deuterium permeation behavior in iron-irradiated erbium oxide coating

Chikada, Takumi; Fujita, Hideyuki; Matsunaga, Moeki; Horikoshi, Seira; Mochizuki, Jumpei; Hu, Cui; Koch, F.; Tokitani, M.; Hishinuma, Yoshimitsu; Yabuuchi, Kiyohiro; Oya, Yasuhisa

doi:10.1016/j.fusengdes.2017.01.016

Cited by 14 publications

(4 citation statements)

References 18 publications

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“…Particularly erbia is considered in the subsequent section. [168][169][170][171][172][173][174][175][176][177][178][179][180][181][182][183]…”

Section: Permeation Barriersmentioning

confidence: 99%

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Fusion Materials Development at Forschungszentrum Jülich

Coenen

2020

Adv Eng Mater

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Material issues pose a significant challenge for the design of future fusion reactors. From a historic point of view, the material mix used for the first wall of a fusion reactor has continually evolved, from original steel vessels to carbon and other low-Z materials such as beryllium to tungsten as the primary candidate for a reactor's first wall armor and divertor material. For materials considered for fusion applications, a highly integrated approach is necessary. Resilience against neutron damage, good power exhaust, and oxidation resistance during accidental air ingress are design relevant issues while deciding on new materials or improving upon baseline materials. Neutron-induced effects, e.g., transmutation adding to embrittlement, retention, and changes to thermomechanical properties, are crucial to material performance. In this contribution, the recent progress (2013-2019) in fusion materials development for current and future fusion devices, at Forschungszentrum Jülich GmbH, with activities focussing on advanced materials and their characterization is given. It is a continuation and extension of the work given by Coenen et al.

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“…Particularly erbia is considered in the subsequent section. [168][169][170][171][172][173][174][175][176][177][178][179][180][181][182][183]…”

Section: Permeation Barriersmentioning

confidence: 99%

“…For studies of other candidate materials, references related to an intensive collaboration with a Japanese group are given. Particularly erbia is considered in the subsequent section …”

Section: Materials For Fusionmentioning

confidence: 99%

Fusion Materials Development at Forschungszentrum Jülich

Coenen

2020

Adv Eng Mater

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“…The preparation of tri-tium permeable barriers (TPBs) on the inner wall of metallic structural materials has been considered a promising solution. A large number of research show that the ceramic coatings, including Al 2 O 3 [1][2][3], Y 2 O 3 [4][5][6], Er 2 O 3 [7][8][9], Cr 2 O 3 [10], other metal oxide coatings, AlN [11] and Si 3 N 2 , other nitride coatings, TiC and SiC [12], and other carbide coatings and their composite coatings, have been demonstrated to be beneficial to reduce tritium permeation flow. Among these TPBs, the Al 2 O 3 ceramic coating, as a promising candidate, has been attached much more attention because of its high permeation resistance performance, outstanding compatibility with Pb-Li, good thermal stability with irradiation and corrosion resistance, and excellent comprehensive properties [13][14][15][16].…”

Section: Introductionmentioning

confidence: 99%

Study on the Influence of Introducing Al Transition Layer on Deuterium Resistance of Al2O3 Coating

Wang

Liu³

et al. 2021

International Journal of Photoenergy

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The Al/Al2O3 composite deuterium barrier was deposited on the polished side of 316 L stainless steel by the method of radio-frequency magnetron sputtering. The influence of the introduction of Al transition layer on the deuterium resistance performance of Al2O3 ceramic coating was studied. The field emission scanning electron microscope (SEM), the grazing incident X-ray diffraction technique (GIXRD), and the auger electron spectroscopy (AES) were used to analyze the microscopic morphology, phase, and element distribution in the depth direction of the Al/Al2O3 coating, and the gas-driver permeation method was used to measure the deuterium permeation behavior of the coating sample. The results show that Al2O3 is amorphous after annealing at 873 K. Due to the oxidation of the Al transition layer, the connection between the coating and the substrate is tightly connected. Under the combined action of permeation temperature and pressure of 873 K and 80 kPa, the deuterium permeability of Al/Al2O3 coating is 6.35 × 10 − 14 mol·m-1·s-1·Pa-0.5, which shows that the Al/Al2O3 coating has excellent deuterium permeation resistance. Furthermore, deuterium permeability of the Al/Al2O3 coating was diminished by about 2 orders of magnitude compared with 316 L stainless steel, and it is reduced 2~3 times compared with the single Al2O3 coating sample. The study indicates that the introduction of the Al transition layer can significantly enhance the barrier effect of the Al/Al2O3 coating sample.

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“…In recent years, owing to the lack of neutron resources, there has been a trend in the scientific community to simulate neutron-induced damages using high-energy ions/electrons in TPB [19,20]. Chikada et al performed a series of experiments to investigate the irradiation effects on deuterium permeation through erbium oxide coatings deposited on reduced activation ferritic steel substrates by 0.01-1 dpa iron-ion irradiation [21][22][23]. They found that all three irradiated samples showed 50%-80% lower permeability than that of unirradiated coatings at the temperature of more than 500 • C. The 0.1 dpa-damaged sample showed an order of magnitude higher permeability than the unirradiated sample at 300 • C-500 • C. It was concluded that the deuterium permeability through the coatings irradiated at elevated temperature is determined by the balance between damage introduction and recovery.…”

Section: Introductionmentioning

confidence: 99%

Influence of irradiation-induced point defects on the dissolution and diffusion properties of hydrogen in α-Al₂O₃: a first-principles study

Pan

Lü

et al. 2021

Nucl. Fusion

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Alpha-alumina (α-Al2O3) is considered to be an ideal candidate material for the tritium permeation barrier (TPB) with excellent tritium resistance properties. However, in a fusion reactor, the irradiation-induced defects could sum up on fabrication-induced defects so to reduce drastically the barrier performance. The underlying mechanism is still not settled. In this paper, the first-principles density functional theory (DFT) approach is used to explore the influence of irradiation-induced point defects on the dissolution and diffusion properties of hydrogen (H) in α-Al2O3. H + − V A l − 3 and H + − V O 0 defects have much lower formation energies at E G/2 in both Al-rich and O-rich growth environments that H atoms are easily captured by vacancy-type irradiation-induced point defects. As a result, higher H retention can be expected, which is consistent with the experimental results. Moreover, by calculating several different diffusion pathways of H-defect complexes and the corresponding diffusion coefficient, it can be inferred that H atoms and vacancy-type point defects can hardly diffuse as a bound entity. Therefore, isolated vacancy-type irradiation-induced point defects can trap multiple H atoms to form H-defect complexes and impede the diffusion process of H, which can enhance the efficiency of protection against H permeation through α-Al2O3 TPB. However, the minimum diffusion barrier for O i H− migration to the first nearest neighbor O interstitial site is 0.44 eV, which is so low that O i H− can migrate quickly at room temperature. This fast diffusion pathway for H could be the underlying mechanism for the low efficiency in preventing H permeation through irradiated α-Al2O3. Our results provide a sound theoretical explanation for recent experimental results of H permeation in α-Al2O3 under irradiation environment.

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Deuterium permeation behavior in iron-irradiated erbium oxide coating

Cited by 14 publications

References 18 publications

Fusion Materials Development at Forschungszentrum Jülich

Fusion Materials Development at Forschungszentrum Jülich

Study on the Influence of Introducing Al Transition Layer on Deuterium Resistance of Al2O3 Coating

Influence of irradiation-induced point defects on the dissolution and diffusion properties of hydrogen in α-Al₂O₃: a first-principles study

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Deuterium permeation behavior in iron-irradiated erbium oxide coating

Cited by 14 publications

References 18 publications

Fusion Materials Development at Forschungszentrum Jülich

Fusion Materials Development at Forschungszentrum Jülich

Study on the Influence of Introducing Al Transition Layer on Deuterium Resistance of Al2O3 Coating

Influence of irradiation-induced point defects on the dissolution and diffusion properties of hydrogen in α-Al2O3: a first-principles study

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Influence of irradiation-induced point defects on the dissolution and diffusion properties of hydrogen in α-Al₂O₃: a first-principles study