Fabrication technology development and characterization of tritium permeation barriers by a liquid phase method

Chikada, Takumi; Matsunaga, Moeki; Horikoshi, Seira; Mochizuki, Jumpei; Fujita, Hideyuki; Hishinuma, Yoshimitsu; Isobe, K.; Hayashi, T.; Terai, Takayuki; Oya, Yasuhisa

doi:10.1016/j.fusengdes.2018.01.054

Cited by 20 publications

(13 citation statements)

References 9 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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“…[11][12][13]. The annealing temperature was 600 ºC because the deterioration of the ZrO2 coating such as cracking occurred at the temperature in the previous research [3]. Considered above, the annealing test was performed at 600 ºC for 24 h in a high vacuum (~10 -6 Pa) in this study.…”

Section: Annealing Testmentioning

confidence: 99%

“…One of the solutions for the problems is to apply a tritium permeation barrier (TPB) on structural materials such as reduced activation ferritic/martensitic (RAFM) steels [1,2]. Ceramics such as zirconium oxide (ZrO2) and yttrium oxide (Y2O3) have been considered as candidate materials for TPB [3,4]. In particular, ZrO2 coatings showed high permeation reduction performance as well as high compatibility with liquid tritium breeders such as lithium-lead [5].…”

Section: Introductionmentioning

confidence: 99%

“…In particular, ZrO2 coatings showed high permeation reduction performance as well as high compatibility with liquid tritium breeders such as lithium-lead [5]. However, it was also found that the deterioration of the coating such as cracking occurred at high temperatures [3]. Meanwhile, yttria-stabilized zirconia (YSZ) produced by the addition of Y2O3 to ZrO2 has better thermal cycle stability and fracture toughness than ZrO2 [6,7].…”

Section: Introductionmentioning

confidence: 99%

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Deuterium permeation behavior through yttria-stabilized zirconia coating fabricated by magnetron sputtering

Endoh

Nakamura

Fujita

et al. 2020

Fusion Engineering and Design

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Layer-structured Cr/CrxN coating via electroplating-based nitridation achieving high deuterium resistance as the hydrogen permeation barrier

Zheng

Zhou

et al. 2022

J Adv Ceram

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Hydrogen isotope permeation through structural materials is a key issue for developing nuclear fusion energy, which will cause fuel loss and radioactive pollution. Developing ceramic coatings with high thermal shock and hydrogen resistance is an effective strategy to solve this issue. In this work, a layer-structured Cr/CrxN coating was successfully fabricated by a facile electroplating-based nitridation technique, which is easy, facile, and applicable to coating complex-shaped substrates. The Cr/CrxN coating, composed of a bottom Fe/Cr interdiffusion zone, a middle Cr layer, and a top CrxN layer, exhibits high bonding strength, high anti-thermal-shock ability, and high deuterium permeation resistance. Its bonding strength achieves 43.6 MPa. The Cr/CrxN coating remains intact even after suffering 300 thermal shock cycles under a 600 °C-water condition. Through optimizing the nitridation temperature, the Cr/CrxN coating achieves a deuterium permeation reduction factor (PRF) as high as 3599 at 500 °C. Considering its scalable fabrication technique and considerable properties, the developed Cr/CrxN coating may serve as a novel high-performance hydrogen permeation barrier in various fields.

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Fabrication technology development and characterization of tritium permeation barriers by a liquid phase method

Cited by 20 publications

References 9 publications

Fusion Materials Development at Forschungszentrum Jülich

Fusion Materials Development at Forschungszentrum Jülich

Deuterium permeation behavior through yttria-stabilized zirconia coating fabricated by magnetron sputtering

Layer-structured Cr/CrxN coating via electroplating-based nitridation achieving high deuterium resistance as the hydrogen permeation barrier

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