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Journal Articles

Tritium removal by isotopic exchange

Tanabe, Tetsuo*; Sugiyama, Kazuyoshi*; Shibahara, Takahiro*; Hirohata, Yuko*; Yoshida, Masafumi; Masaki, Kei; Sato, Masayasu

Journal of Nuclear Materials, 390-391, p.705 - 708, 2009/06

 Times Cited Count:8 Percentile:49.6(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Hydrogen retention and carbon deposition in plasma facing components and the shadowed area of JT-60U

Masaki, Kei; Tanabe, Tetsuo*; Hirohata, Yuko*; Oya, Yasuhisa*; Shibahara, Takahiro*; Hayashi, Takao; Sugiyama, Kazuyoshi*; Arai, Takashi; Okuno, Kenji*; Miya, Naoyuki

Nuclear Fusion, 47(11), p.1577 - 1582, 2007/11

 Times Cited Count:14 Percentile:45.29(Physics, Fluids & Plasmas)

In JT-60U, erosion/deposition analyses for the plasma facing wall have shown that deposition was dominant at the inner-middle first wall and the inner divertor, whereas erosion dominant at the upper first wall and the outer divertor. Assuming toroidal symmetry in the erosion and deposition patterns, the net carbon erosion and deposition in the divertor area were estimated to be 0.34 kg and 0.55 kg, respectively. In a whole, the increment of carbon in the divertor region was 0.21 kg, which should be originated from the first wall. The hydrogen concentration in the thick deposition layer of the inner divertor was 0.02 in (H+D)/C. In the plasma-shadowed area underneath the divertor region at around 420 K, re-deposited layers of 2 $$mu$$m-thick were found with high hydrogen concentration of 0.8 in (H+D)/C. The carbon deposition rate in the plasma-shadowed area, however, was 8$$times$$10$$^{19}$$ atoms/s, which was one order smaller than that (6$$times$$10$$^{20}$$ atoms/s) on the wall surface.

Journal Articles

Hydrogen retention and carbon deposition in plasma facing wall and shadowed area of JT-60U

Masaki, Kei; Tanabe, Tetsuo*; Hirohata, Yuko*; Oya, Yasuhisa*; Shibahara, Takahiro*; Hayashi, Takao; Sugiyama, Kazuyoshi*; Arai, Takashi; Okuno, Kenji*; Miya, Naoyuki

Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03

Evaluation of fuel inventory and its retention process are critical issues for a next-step fusion device, especially with carbon-based wall. In order to resolve the issues, the hydrogen retention and carbon deposition analyses for the plasma facing surfaces and plasma-shadowed area of JT-60U have been performed. In JT-60U, erosion/deposition analyses for the plasma facing wall have shown that deposition was dominant at the inner-middle first wall and the inner divertor, whereas erosion dominant at the upper first wall and the outer divertor. Assuming toroidal symmetry in the erosion and deposition patterns, the net carbon erosion and deposition in the divertor area were estimated to be 0.34 kg and 0.55 kg, respectively. In a whole, the increment of carbon in the divertor region was 0.21 kg, which should be originated from the first wall. The hydrogen concentration in the thick deposition layer of the inner divertor was $$sim$$0.02 in (H+D)/C. In the plasma-shadowed area underneath the divertor region at around 420 K, re-deposited layers of $$sim$$2$$mu$$m-thick were found with high hydrogen concentration of $$sim$$0.8 in (H+D)/C. The carbon deposition rate in the plasma-shadowed area, however, was 8$$times$$10$$^{19}$$ atoms/s, which was one order smaller than that (6$$times$$10$$^{20}$$ atoms/s) on the wall surface.

Journal Articles

Hydrogen isotope retention of JT-60U W-shaped divertor tiles exposed to DD discharges

Shibahara, Takahiro*; Tanabe, Tetsuo*; Hirohata, Yuko*; Oya, Yasuhisa*; Oyaizu, Makoto*; Yoshikawa, Akira*; Onishi, Yoshihiro*; Arai, Takashi; Masaki, Kei; Okuno, Kenji*; et al.

Journal of Nuclear Materials, 357(1-3), p.115 - 125, 2006/10

 Times Cited Count:20 Percentile:78.89(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Hydrogen retention of JT-60 open divertor tiles exposed to HH discharges

Shibahara, Takahiro*; Tanabe, Tetsuo*; Hirohata, Yuko*; Oya, Yasuhisa*; Oyaizu, Makoto*; Yoshikawa, Akira*; Onishi, Yoshihiro*; Arai, Takashi; Masaki, Kei; Okuno, Kenji*; et al.

Nuclear Fusion, 46(10), p.841 - 847, 2006/10

 Times Cited Count:17 Percentile:52.52(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Hydrogen isotope distributions and retentions in the inner divertor tile of JT-60U

Oya, Yasuhisa*; Hirohata, Yuko*; Tanabe, Tetsuo*; Shibahara, Takahiro*; Kimura, Hiromi*; Oyaizu, Makoto*; Arai, Takashi; Masaki, Kei; Goto, Yoshitaka*; Okuno, Kenji*; et al.

Fusion Engineering and Design, 75-79, p.945 - 949, 2005/11

 Times Cited Count:9 Percentile:53.26(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Retention of hydrogen isotopes in divertor tiles used in JT-60U

Hirohata, Yuko*; Shibahara, Takahiro*; Tanabe, Tetsuo*; Oya, Yasuhisa*; Arai, Takashi; Goto, Yoshitaka*; Masaki, Kei; Yagyu, Junichi; Oyaizu, Makoto*; Okuno, Kenji*; et al.

Fusion Science and Technology, 48(1), p.557 - 560, 2005/07

 Times Cited Count:3 Percentile:24.27(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Retention characteristics of hydrogen isotopes in JT-60U

Masaki, Kei; Sugiyama, Kazuyoshi*; Hayashi, Takao; Ochiai, Kentaro; Goto, Yoshitaka*; Shibahara, Takahiro*; Hirohata, Yuko*; Oya, Yasuhisa*; Miya, Naoyuki; Tanabe, Tetsuo*

Journal of Nuclear Materials, 337-339, p.553 - 559, 2005/03

 Times Cited Count:26 Percentile:84.04(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Hydrogen retention in divertor tiles used in JT-60 for hydrogen discharge period

Hirohata, Yuko*; Shibahara, Takahiro*; Tanabe, Tetsuo*; Arai, Takashi; Goto, Yoshitaka*; Oya, Yasuhisa*; Yoshida, Hajime*; Morimoto, Yasutomi*; Yagyu, Junichi; Masaki, Kei; et al.

Journal of Nuclear Materials, 337-339, p.609 - 613, 2005/03

 Times Cited Count:13 Percentile:65.49(Materials Science, Multidisciplinary)

no abstracts in English

Oral presentation

Retention behavior of hydrogen isotopes on JT-60U carbon tiles

Shibahara, Takahiro*; Hirohata, Yuko*; Oya, Yasuhisa*; Oyaizu, Makoto*; Onishi, Yoshihiro*; Yoshikawa, Akira*; Okuno, Kenji*; Sugiyama, Kazuyoshi*; Tanabe, Tetsuo*; Arai, Takashi; et al.

no journal, , 

no abstracts in English

Oral presentation

Distribution of hydrogen isotopes retained in the tile located in the divertor region of JT-60U

Hirohata, Yuko*; Tanabe, Tetsuo*; Sugiyama, Kazuyoshi*; Shibahara, Takahiro*; Oya, Yasuhisa*; Oyaizu, Makoto*; Yoshikawa, Akira*; Okuno, Kenji*; Masaki, Kei; Arai, Takashi; et al.

no journal, , 

no abstracts in English

Oral presentation

Hydrogen removal properties from JT-60 open divertor tile by pulsed laser ablation

Miya, Naoyuki; Watanabe, Daisuke*; Sakawa, Yoichi*; Shibahara, Takahiro*; Sugiyama, Kazuyoshi*; Shoji, Tatsuo*; Yamazaki, Kozo*; Masaki, Kei; Tanabe, Tetsuo*

no journal, , 

no abstracts in English

Oral presentation

Carbon deposition/erosion and retention of hydrogen isotopes in JT-60U

Hirohata, Yuko*; Tanabe, Tetsuo*; Oya, Yasuhisa*; Shibahara, Takahiro*; Sugiyama, Kazuyoshi*; Oyaizu, Makoto*; Yoshikawa, Akira*; Yoshida, Masashi*; Arai, Takashi; Masaki, Kei; et al.

no journal, , 

no abstracts in English

Oral presentation

Carbon deposition/erosion and retention of hydrogen isotopes in JT-60U

Hirohata, Yuko*; Tanabe, Tetsuo*; Oya, Yasuhisa*; Shibahara, Takahiro*; Sugiyama, Kazuyoshi*; Oyaizu, Makoto*; Yoshikawa, Akira*; Yoshida, Masashi*; Arai, Takashi; Masaki, Kei; et al.

no journal, , 

no abstracts in English

Oral presentation

Development of advanced reprocessing system using high selective and controllable precipitants, 6; Investigation on thermal decomposition behaviors of uranium-pyrrolidone compounds and fuel production steps

Shibahara, Takahiro*; Chikazawa, Takahiro*; Kikuchi, Toshiaki*; Nishimura, Kenji*; Morita, Yasuji; Ikeda, Yasuhisa*

no journal, , 

Thermal decomposition of precipitants of U(VI) with pyrrolidone derivatives was investigated for the development of an advanced reprocessing system for spent FBR fuels based only on precipitation method using the pyrrolidone derivatives. We have examined N-cyclohexyl-2-pyrrolidone (NCP), N-n-butyl-2-pyrrolidone (NBP) and N-propyl-2-pyrrolidone (NProP) as the precipitants. It was found that U(VI) precipitates with those precipitants were decomposed at higher than 450 $$^{circ}$$C and such thermal treatment produced U oxides with low impurities.

Oral presentation

Development of advanced reprocessing system using highly selective and controllable precipitants, 13; Investigation on thermal decomposition behavior of uranium(VI)-pyrrolidone

Shibahara, Takahiro*; Nagata, Masanobu*; Chikazawa, Takahiro*; Kikuchi, Toshiaki*; Morita, Yasuji; Ikeda, Yasuhisa*

no journal, , 

Thermal decomposition of precipitants of U(VI) with pyrrolidone derivatives was investigated for the development of an advanced reprocessing system for spent FBR fuels based only on precipitation method using the pyrrolidone derivatives. It was found that the thermal treatment of U(VI) precipitates at constant temperature of 150 - 170 $$^{circ}$$C before the decomposition of the precipitate at high temperature contribute to the production of the U oxides with low impurities and the recovery of the with pyrrolidone derivatives.

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