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Journal Articles

Concentration profiles of tritium penetrated into concrete

Takata, Hiroki*; Furuichi, Kazuya*; Nishikawa, Masabumi*; Fukada, Satoshi*; Katayama, Kazunari*; Takeishi, Toshiharu*; Kobayashi, Kazuhiro; Hayashi, Takumi; Namba, Haruyuki*

Fusion Science and Technology, 54(1), p.223 - 226, 2008/07

 Times Cited Count:8 Percentile:45.92(Nuclear Science & Technology)

Concentration profiles of tritium penetrated into cement paste, mortar and concrete were measured by using samples with a shape of column. Tritium penetrated until a location of about 5 cm from the exposed surface after 6 months' exposure. The amount of tritium penetrated into mortar and concrete were less than 70% and half that into cement paste.

Journal Articles

Studies on the behavior of tritium in components and structure materials of tritium confinement and detritiation systems of ITER

Kobayashi, Kazuhiro; Isobe, Kanetsugu; Iwai, Yasunori; Hayashi, Takumi; Shu, Wataru; Nakamura, Hirofumi; Kawamura, Yoshinori; Yamada, Masayuki; Suzuki, Takumi; Miura, Hidenori*; et al.

Nuclear Fusion, 47(12), p.1645 - 1651, 2007/12

 Times Cited Count:3 Percentile:87.21(Physics, Fluids & Plasmas)

The confinement and removal of tritium are the key subjects for safety of ITER. The ITER buildings are confinement barriers of tritium. In a hot cell building, tritium is often released, as vapor and is in contact with the inner walls. Also those of an ITER tritium plant building will be exposed to tritium in an accident. However, the data are scarce, especially on the penetration of tritium into the concrete of the wall materials. The tritium released in the buildings is removed by the Atmosphere Detritiation Systems (ADS), where the tritium is oxidized by catalysts and is removed as water. Special gas of SF$$_{6}$$ is used in ITER, and is expected to be released in an accident such as fire. Although the SF$$_{6}$$ gas has the potential as a catalyst poison, the performance of ADS with the existence of SF$$_{6}$$ has not been confirmed yet. Tritiated water is produced in the regeneration process of ADS, and is subsequently processed by the ITER Water Detritiation System (WDS). One of the key components of WDS is an electrolysis cell. The electrolysis cell is made of organic compounds, and there is no data on the durability of the cell exposed to tritium. To overcome these issues in a global tritium confinement, a series of experimental studies have been carried out as an ITER R&D task: (1) tritium behavior in concrete; (2) effect of SF$$_{6}$$ on performance of ADS; and (3) tritium durability of electrolysis cell of ITER-WDS.

Journal Articles

Research and development of nuclear fusion

Ushigusa, Kenkichi; Seki, Masahiro; Ninomiya, Hiromasa; Norimatsu, Takayoshi*; Kamada, Yutaka; Mori, Masahiro; Okuno, Kiyoshi; Shibanuma, Kiyoshi; Inoue, Takashi; Sakamoto, Keishi; et al.

Genshiryoku Handobukku, p.906 - 1029, 2007/11

no abstracts in English

Journal Articles

Chemical form of released tritium from solid breeder materials under the various purge gas conditions

Kinjo, Tomohiro*; Nishikawa, Masabumi*; Yanashita, Naoya*; Koyama, Takanori*; Tanifuji, Takaaki*; Enoeda, Mikio

Fusion Engineering and Design, 82(15-24), p.2147 - 2151, 2007/10

 Times Cited Count:16 Percentile:23.78(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Estimation of tritium release behavior from solid breeder materials under the condition of ITER test blanket module

Kinjo, Tomohiro*; Nishikawa, Masabumi*; Enoeda, Mikio

Journal of Nuclear Materials, 367-370(2), p.1361 - 1365, 2007/08

 Times Cited Count:22 Percentile:15.9(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Studies on behavior of tritium in components and structure materials of tritium confinement and detritiation systems of ITER

Kobayashi, Kazuhiro; Isobe, Kanetsugu; Iwai, Yasunori; Hayashi, Takumi; Shu, Wataru; Nakamura, Hirofumi; Kawamura, Yoshinori; Yamada, Masayuki; Suzuki, Takumi; Miura, Hidenori*; et al.

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

no abstracts in English

Journal Articles

Tritium release from bulk of carbon-based tiles used in JT-60U

Takeishi, Toshiharu*; Katayama, Kazunari*; Nishikawa, Masabumi*; Masaki, Kei; Miya, Naoyuki

Journal of Nuclear Materials, 349(3), p.327 - 338, 2006/03

 Times Cited Count:6 Percentile:55.2(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Tritium release behavior from JT-60U vacuum vessel during air exposure phase and wall conditioning phase

Isobe, Kanetsugu; Nakamura, Hirofumi; Kaminaga, Atsushi; Higashijima, Satoru; Nishi, Masataka; Konishi, Satoshi*; Nishikawa, Masabumi*; Tanabe, Tetsuo*

Fusion Science and Technology, 48(1), p.302 - 305, 2005/07

 Times Cited Count:3 Percentile:73.42(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Release behavior of hydrogen isotopes from JT-60U graphite tiles

Katayama, Kazunari*; Takeishi, Toshiharu*; Nagase, Hiroyasu*; Manabe, Yusuke*; Nishikawa, Masabumi*; Miya, Naoyuki; Masaki, Kei

Fusion Science and Technology, 48(1), p.561 - 564, 2005/07

 Times Cited Count:0 Percentile:100(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:73.42(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Recovery of retained tritium from graphite tile of JT-60U

Takeishi, Toshiharu*; Katayama, Kazunari*; Nishikawa, Masabumi*; Miya, Naoyuki; Masaki, Kei

Fusion Science and Technology, 48(1), p.565 - 568, 2005/07

 Times Cited Count:1 Percentile:88.5(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Tritium release behavior from the graphite tiles used at the dome unit of the W-shaped divertor region in JT-60U

Katayama, Kazunari*; Takeishi, Toshiharu*; Manabe, Yusuke*; Nagase, Hiroyasu*; Nishikawa, Masabumi*; Miya, Naoyuki

Journal of Nuclear Materials, 340(1), p.83 - 92, 2005/04

 Times Cited Count:7 Percentile:56.28(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Major results of the cooperative program between JAERI and universities using plasma facing materials in JT-60U

Miya, Naoyuki; Tanabe, Tetsuo*; Nishikawa, Masabumi*; Okuno, Kenji*; Hirohata, Yuko*; Oya, Yasuhisa*

Journal of Nuclear Materials, 329-333(1), p.74 - 80, 2004/08

 Times Cited Count:12 Percentile:34.84(Materials Science, Multidisciplinary)

no abstracts in English

JAEA Reports

Analysis of exhaust gas composition in JT-60U discharge cleaning experiments

Horikawa, Toyohiko*; Kaminaga, Atsushi; Nakamura, Hirofumi; Higashijima, Satoru; Arai, Takashi; Kubo, Hirotaka; Konishi, Satoshi*; Nishikawa, Masabumi*

JAERI-Tech 2003-082, 66 Pages, 2003/12

JAERI-Tech-2003-082.pdf:3.44MB

no abstracts in English

Journal Articles

Isotope exchange reactions on ceramic breeder materials and their effect on tritium inventory

Nishikawa, Masabumi*; *; Kawamura, Yoshinori; Nishi, Masataka

JAERI-Conf 98-006, p.170 - 182, 1998/03

no abstracts in English

Journal Articles

Tritium inventory estimation in solid blanket system

Nishikawa, Masabumi*; Baba, Atsushi*; *; Kawamura, Yoshinori

Fusion Engineering and Design, 39-40, p.615 - 625, 1998/00

 Times Cited Count:14 Percentile:24.86(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Tritium behavior in fusion reactor facilities and the environment, 3; Tritium behavior in fusion fuel systems

Yamanishi, Toshihiko; Nishikawa, Masabumi*; *

Purazuma, Kaku Yugo Gakkai-Shi, 73(12), p.1326 - 1332, 1997/12

no abstracts in English

Journal Articles

Isotope exchange capacity of solid breeder materials

Baba, Atsushi*; Nishikawa, Masabumi*; Kawamura, Yoshinori; Okuno, Kenji

Journal of Nuclear Materials, 248, p.106 - 110, 1997/09

 Times Cited Count:4 Percentile:61.05(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Formation of water in lithium ceramics bed at hydrogen addition to purge gas

Kawamura, Yoshinori; Nishikawa, Masabumi*; *; Okuno, Kenji

Journal of Nuclear Materials, 230, p.287 - 294, 1996/00

 Times Cited Count:37 Percentile:6.14

no abstracts in English

Journal Articles

Recovery of hydrogen isotopes and impurity mixture by cryogenic molecular sieve bed for GDC gas cleanup

Enoeda, Mikio; Kawamura, Yoshinori; Okuno, Kenji; Tanaka, Kenichi*; Uetake, Mitsuru*; Nishikawa, Masabumi*

Fusion Technology, 28(3), p.591 - 596, 1995/10

no abstracts in English

32 (Records 1-20 displayed on this page)