Search Results - "Oya, Yasuhisa"

Lithium-lead corrosion behavior of erbium oxide, yttrium oxide and zirconium oxide coatings fabricated by metal organic decomposition by Matsunaga, Moeki, Horikoshi, Seira, Mochizuki, Jumpei, Fujita, Hikari, Hishinuma, Yoshimitsu, Isobe, Kanetsugu, Hayashi, Takumi, Terai, Takayuki, Oya, Yasuhisa, Chikada, Takumi

“…Tritium permeation through and corrosion of structural materials are critical issues in fusion reactor liquid lithium-lead blanket concepts from the viewpoints…”
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Preparation of Li2TiO3 by hydrothermal synthesis and its structure evolution under high energy Ar+ irradiation by Zhou, Qilai, Oya, Yasuhisa, Chikada, Takumi, Zhang, Wen, Xue, Lihong, Yan, Youwei

“…Ultrafine lithium titanate (Li2TiO3) powder was synthesized by hydrothermal method. The phase formation and transition condition among α, β, and γ-Li2TiO3 were…”
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Deuterium permeation and retention behaviors in erbium oxide-iron multilayer coatings by Horikoshi, Seira, Mochizuki, Jumpei, Oya, Yasuhisa, Chikada, Takumi

“…•Deuterium permeation behavior in ceramics-metal multilayer coatings were investigated.•The grain boundary diffusion model was established with deuterium depth…”
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Preparation and characterization of Er2O3-ZrO2 multi-layer coating for tritium permeation barrier by metal organic decomposition by Mochizuki, Jumpei, Horikoshi, Seira, Fujita, Hikari, Matsunaga, Moeki, Hishinuma, Yoshimitsu, Oya, Yasuhisa, Chikada, Takumi

“…Tritium permeation barrier coatings have been investigated for several decades to control tritium migration in fusion reactor fuel systems. In liquid…”
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Tritium trapping states induced by lithium-depletion in Li 2 TiO 3 by Kobayashi, Makoto, Oya, Yasuhisa, Okuno, Kenji

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Numerical analysis of deuterium migration behaviors in tungsten damaged by fast neutron by means of gas absorption method by Kobayashi, Makoto I, Shimada, Masashi, Taylor, Chase N, Nobuta, Yuji, Hatano, Yuji, Oya, Yasuhisa

“…Deuterium retention behavior in tungsten damaged by fast neutrons at high temperatures (0.43 dpa at 918 K and 0.74 dpa at 1079 K) and 6.4 MeV Fe2+ (0.3 dpa at…”
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Helium and hydrogen interaction in tungsten simultaneously irradiated by He+-H2+ at high temperature by Zhou, Qilai, Togari, Akihiro, Nakata, Moeko, Zhao, Mingzhong, Sun, Fei, Yajima, Miyuki, Tokitani, Masayuki, Masuzaki, Suguru, Yoshida, Naoaki, Hara, Masanori, Hatano, Yuji, Oya, Yasuhisa

“…Tungsten (W) is one of the most promising candidates for plasma facing materials in the fusion reactor. Helium (He) in W can influence the retention of…”
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Effect of helium irradiation on deuterium permeation behavior in tungsten by Uemura, Yuki, Sakurada, Shodai, Fujita, Hiroe, Azuma, Keisuke, Zhou, Quilai, Hatano, Yuji, Yoshida, Naoaki, Watanabe, Hideo, Oyaizu, Makoto, Isobe, Kanetsugu, Shimada, Masashi, Buchenauer, Dean, Kolasinski, Robert, Chikada, Takumi, Oya, Yasuhisa

“…In this study, we measured deuterium (D) gas-driven permeation through tungsten (W) foils that had been pre-damaged by helium ions (He+). The goal of this work…”
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Deuterium permeation behavior of tritium permeation barrier coating containing carbide nanoparticles by Mochizuki, Jumpei, Horikoshi, Seira, Oya, Yasuhisa, Chikada, Takumi

“…•Y2O3 coatings with carbide nanoparticles were fabricated by metal organic decomposition.•Deuterium permeation through Y2O3 coatings containing carbide…”
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Kinetics of double strand breaks of DNA in tritiated water evaluated using single molecule observation method by Hatano, Yuji, Konaka, Yuna, Shimoyachi, Hiroto, Kenmotsu, Takahiro, Oya, Yasuhisa, Nakamura, Hiroaki

“…•Double strand breaks of DNA molecules in tritiated water (5.2 MBq/cm3) was successfully evaluated under the sterilized conditions.•The rate of double strand…”
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Fabrication technology development and characterization of tritium permeation barriers by a liquid phase method by Chikada, Takumi, Matsunaga, Moeki, Horikoshi, Seira, Mochizuki, Jumpei, Fujita, Hikari, Hishinuma, Yoshimitsu, Isobe, Kanetsugu, Hayashi, Takumi, Terai, Takayuki, Oya, Yasuhisa

“…Tritium permeation through structural materials is one of critical issues in liquid lithium-lead blanket concepts from the viewpoints of an efficient fuel…”
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Deuterium permeation behavior and its iron-ion irradiation effect in yttrium oxide coating deposited by magnetron sputtering by Chikada, Takumi, Fujita, Hikari, Engels, Jan, Houben, Anne, Mochizuki, Jumpei, Horikoshi, Seira, Matsunaga, Moeki, Tokitani, Masayuki, Hishinuma, Yoshimitsu, Kondo, Sosuke, Yabuuchi, Kiyohiro, Schwarz-Selinger, Thomas, Terai, Takayuki, Oya, Yasuhisa

“…Tritium permeation through structural materials is a critical issue in fusion reactors from the viewpoints of sufficient fuel balance and radiological hazard…”
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Deuterium recombination coefficient on tungsten surface determined by plasma driven permeation by Zhao, Mingzhong, Yamazaki, Shota, Wada, Takuro, Koike, Ayaka, Sun, Fei, Ashikawa, Naoko, Someya, Yoji, Mieno, Tetsu, Oya, Yasuhisa

“…•Deuterium plasma driven permeation experiments were performed for W rod sample.•Deuterium recombination coefficient on W surface is obtained by combing the…”
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Effect of carbon impurity reduction on hydrogen isotope retention in QUEST high temperature wall by Oya, Yasuhisa, Sano, Atsuko, Sato, Yurina, Nakata, Moeko, Zhou, Qilai, Togari, Akihiro, Yoshida, Naoaki, Hanada, Kazuaki

“…The W (tungsten) samples were placed at top, equator and bottom walls of QUEST (Q-shu University Experiment with Steady-State Spherical Tokamak) device and…”
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Deuterium permeation through monoclinic erbium oxide coating by Chikada, Takumi, Fujita, Hikari, Tokitani, Masayuki, Hishinuma, Yoshimitsu, Terai, Takayuki, Oya, Yasuhisa

“…Erbium oxide has been investigated as a tritium permeation barrier material in a D-T fusion reactor fuel system for more than a decade. Erbium oxide normally…”
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Defect annealing and thermal desorption of deuterium in low dose HFIR neutron-irradiated tungsten by Shimada, Masashi, Hara, Masanori, Otsuka, Teppei, Oya, Yasuhisa, Hatano, Yuji

“…Three tungsten samples irradiated at High Flux Isotope Reactor at Oak Ridge National Laboratory were exposed to deuterium plasma (ion fluence of 1×1026m−2) at…”
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Review of recent japanese activities on tritium accountability in fusion reactors by Fukada, Satoshi, Oya, Yasuhisa, Hatano, Yuji

“…•Review of Japanese tritium-safety research is given from several viewpoints.•The keywords are tritium accountability and self sufficiency.•Tritium-relating…”
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Neutron irradiated tungsten bulk defect characterization by positron annihilation spectroscopy by Taylor, Chase N., Shimada, Masashi, Watkins, Joseph M., Hu, Xunxiang, Oya, Yasuhisa

“…•Positron annihilation spectroscopy was performed on neutron irradiated tungsten.•Coincidence doppler broadening measurements show likely and potential…”
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Co-deposited layers on gap surfaces of bulk tungsten divertor tiles in JET ITER-like wall: Directional effects and nanostructures by Tokitani, Masayuki, Miyamoto, Mitsutaka, Masuzaki, Suguru, Hatano, Yuji, Lee, Sun Eui, Oya, Yasuhisa, Kurotaki, Hironori, Asakura, Nobuyuki, Nakamura, Hirofumi, Hayashi, Takumi, Rubel, Marek, Widdowson, Anna, Likonen, Jari

“…•Co-deposited layers formed on the poloidal gap surface of bulk tungsten divertor tiles (W lamellae) from the first campaign of JET with the ITER-Like Wall…”
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Surface chemistry of neutron irradiated tungsten in a high-temperature multi-material environment by Taylor, Chase N., Shimada, Masashi, Nobuta, Yuji, Kobayashi, Makoto I., Oya, Yasuhisa, Hatano, Yuji, Koyanagi, Takaaki

“…•XPS of neutron irradiated tungsten reveals multi-material interactions that occur during months-long reactor irradiations.•The state of surface chemistry is…”
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