Effect of cyclic heat loading on pure tungsten for the ITER divertor by Fukuda, M., Seki, Y., Ezato, K., Yokoyama, K., Nishi, H., Suzuki, S.

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Performance evaluation of tungsten for ITER divertor toward mass production by Fukuda, M., Seki, Y., Ezato, K., Yokoyama, K., Nishi, H., Suzuki, S., Hirai, T.

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Status of technology R&D for the ITER tungsten divertor monoblock by Hirai, T., Escourbiac, F., Barabash, V., Durocher, A., Fedosov, A., Ferrand, L., Jokinen, T., Komarov, V., Merola, M., Carpentier-Chouchana, S., Arkhipov, N., Kuznetcov, V., Volodin, A., Suzuki, S., Ezato, K., Seki, Y., Riccardi, B., Bednarek, M., Gavila, P.

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Design, research and development for plasma facing components in JT-60SA by Tsuru, D, Fukumoto, M, Hayashi, T, Takechi, M, Nakamura, S, Matsunaga, G, Seki, Y, Ezato, K, Suzuki, S

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Development of tungsten divertor components for ITER in Japan by Ezato, K., Suzuki, S., Seki, Y., Hirayama, T., Yamada, H., Escourbiac, F., Hirai, T.

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Characterization of thick plasma spray tungsten coating on ferritic/martensitic steel F82H for high heat flux armor by Yahiro, Y., Mitsuhara, M., Tokunakga, K., Yoshida, N., Hirai, T., Ezato, K., Suzuki, S., Akiba, M., Nakashima, H.

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High heat loading properties of vacuum plasma spray tungsten coatings on reduced activation ferritic/martensitic steel by Tokunaga, K., Hotta, T., Araki, K., Miyamoto, Y., Fujiwara, T., Hasegawa, M., Nakamura, K., Ezato, K., Suzuki, S., Enoeda, M., Akiba, M., Nagasaka, T., Kasada, R., Kimura, A.

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Progress of ITER full tungsten divertor technology qualification in Japan by Ezato, K., Suzuki, S., Seki, Y., Mohri, K., Yokoyama, K., Escourbiac, F., Hirai, T., Kuznetcov, V.

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Effects of high heat flux hydrogen and helium mixture beam irradiation on surface modification and hydrogen retention in tungsten materials by Tokunaga, K., Fujiwara, T., Ezato, K., Suzuki, S., Akiba, M., Kurishita, H., Nagata, S., Tsuchiya, B., Tonegawa, A., Yoshida, N.

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Application of tritium tracer techniques to observation of hydrogen on surface and in bulk of F82H by Otsuka, T., Tanabe, T., Tokunaga, K., Yoshida, N., Ezato, K., Suzuki, S., Akiba, M.

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Design study of fusion DEMO plant at JAERI by Tobita, K., Nishio, S., Enoeda, M., Sato, M., Isono, T., Sakurai, S., Nakamura, H., Sato, S., Suzuki, S., Ando, M., Ezato, K., Hayashi, T., Hirose, T., Inoue, T., Kawamura, Y., Koizumi, N., Kudo, Y., Kurihara, R., Kuroda, T., Matsukawa, M., Mouri, K., Nakamura, Y., Nishi, M., Nomoto, Y., Ohmori, J., Oyama, N., Sakamoto, K., Suzuki, T., Takechi, M., Tanigawa, H., Tsuchiya, K., Tsuru, D.

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Deuterium retention in F82H after low energy hydrogen ion irradiation by Ito, T., Yamauchi, Y., Hino, T., Shibayama, T., Nobuta, Y., Ezato, K., Suzuki, S., Akiba, M.

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Synergistic effects of high heat loading and helium irradiation of tungsten by Tokunaga, K, Tamura, S, Yoshida, N, Ezato, K, Taniguchi, M, Sato, K, Suzuki, S, Akiba, M

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Thermo-hydraulic testing and integrity of ITER Test Blanket Module (TBM) First Wall mock-up in JAEA by Ezato, K., Seki, Y., Tanigawa, H., Hirose, T., Tsuru, D., Nishi, H., Dairaku, M., Yokoyama, K., Suzuki, S., Enoeda, M.

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R&D of a Li2TiO3 pebble bed for a test blanket module in JAEA by Tanigawa, H, Hoshino, T, Kawamura, Y, Nakamichi, M, Ochiai, K, Akiba, M, Ando, M, Enoeda, M, Ezato, K, Hayashi, K, Hirose, T, Konno, C, Nakamura, H, Nozawa, T, Ogiwara, H, Seki, Y, Tsuchiya, K, Tsuru, D, Yamanishi, T

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Determination of Hydrogen Diffusion Coefficients in F82H by Hydrogen Depth Profiling with a Tritium Imaging Plate Technique by Higaki, M., Otsuka, T., Tokunaga, K., Hashizume, K., Ezato, K., Suzuki, S., Enoeda, M., Akiba, M.

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SlimCS—compact low aspect ratio DEMO reactor with reduced-size central solenoid by Tobita, K, Nishio, S, Sato, M, Sakurai, S, Hayashi, T, Shibama, Y.K, Isono, T, Enoeda, M, Nakamura, H, Sato, S, Ezato, K, Hirose, T, Ide, S, Inoue, T, Kamada, Y, Kawamura, Y, Kawashima, H, Koizumi, N, Kurita, G, Nakamura, Y, Mouri, K, Nishitani, T, Ohmori, J, Oyama, N, Sakamoto, K, Suzuki, S, Suzuki, T, Tanigawa, H, Tsuchiya, K, Tsuru, D

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Critical heat flux experiments using a screw tube under DEMO divertor-relevant cooling conditions by Ezato, K., Suzuki, S., Dairaku, M., Akiba, M.

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Deuterium concentration of co-deposited carbon layer produced at gap of wall tiles by Nobuta, Y., Yokoyama, K., Kanazawa, J., Yamauchi, Y., Hino, T., Suzuki, S., Ezato, K., Enoeda, M., Akiba, M.

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Studies of power exhaust and divertor design for a 1.5 GW-level fusion power DEMO by Asakura, N., Hoshino, K., Suzuki, S., Tokunaga, S., Someya, Y., Utoh, H., Kudo, H., Sakamoto, Y., Hiwatari, R., Tobita, K., Shimizu, K., Ezato, K., Seki, Y., Ohno, N., Ueda, Y.

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