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Journal Articles

Improvements in plastic enclosure system for glovebox decommissioning

Watahiki, Masatoshi; Akai, Masanori; Nakai, Koji; Iemura, Keisuke; Yoshino, Masanori*; Hirano, Hiroshi*; Kitamura, Akihiro; Suzuki, Kazunori

Nippon Genshiryoku Gakkai Wabun Rombunshi, 11(1), p.101 - 109, 2012/02

Gloveboxes used for plutonium fuel development and fabrication are eventually dismantled for replacement or decommissioning. Since equipment interior and the inner surface of gloveboxes are contaminated in radioactive materials, glovebox dismantling work is performed by workers wearing an air fed suit with mechanical tools in a plastic enclosure system to control the spread of contamination. Various improvements of enclosure system are implemented including modification of the rooms to decontaminate and undress the air fed suit and introduction of inflammable filter and safety film near the size reduction workspace against fire. We describe the countermeasures deployed in the enclosure system against potential hazards and how these devices work in the real dismantling activities.

Journal Articles

Decommissioning plutonium fuel fabrication facility

Iemura, Keisuke; Nakai, Koji; Watahiki, Masatoshi; Kitamura, Akihiro; Suzuki, Kazunori; Aoki, Yoshikazu

Dekomisshoningu Giho, (43), p.2 - 9, 2011/03

Plutonium fuel fabrication facility is constructed in 1972 and it is almost 40 years of age and equipment and components comprises the facility start degrading. Therefore we need to start dismantling gloveboxes from old ones first and at the same time to maintain the facility components and structures and gloveboxes as necessary. Also, since waste storage space is limited in the site, we effectively use open spaces generated after removing gloveboxes and equipment as temporal waste storage space. After shipping these wastes from the facility, final characterization of the facility will be conducted and demolition of the facility will be take place.

Journal Articles

Technology development for the construction of the ITER superconducting magnet system

Okuno, Kiyoshi; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Kawano, Katsumi; Koizumi, Norikiyo; Hamada, Kazuya; Nunoya, Yoshihiko; Matsui, Kunihiro; Nabara, Yoshihiro; et al.

Nuclear Fusion, 47(5), p.456 - 462, 2007/05

 Times Cited Count:7 Percentile:70.52(Physics, Fluids & Plasmas)

no abstracts in English

Journal Articles

Technology development for the construction of ITER superconducting magnet system

Okuno, Kiyoshi; Nakajima, Hideo; Sugimoto, Makoto; Isono, Takaaki; Kawano, Katsumi; Koizumi, Norikiyo; Hamada, Kazuya; Nunoya, Yoshihiko; Nabara, Yoshihiro; Kitamura, Kazunori; et al.

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

The ITER superconducting magnet system consists of 18 TF coils, one CS and six Poloidal Field (PF) coils. Among six PTs, Japan, EU and US will be responsible for major part of the superconducting magnets, and Japanese contribution will be the largest, including the following four areas: part of TF conductors, about half (9 out of 19) of TF coil winding packs, most of TF coil structures and part of CS conductor. Since 2004, Japan Atomic Energy Agency (JAEA) started preparation activities for procurement, including manufacturing studies to identify detailed fabrication processes and tools for critical components, such as TF coil winding and case, and manufacturing demonstrations at full scale level on Nb$$_{3}$$Sn strands and conductors and cryogenic structural materials, such as coil case segments and radial plates. Details are described in the following sections.

Journal Articles

New conceptual design of a test module assembly for tritium permeation experiment

Ohira, Shigeru; Luo, G.; Nakamura, Hirofumi; Shu, Wataru; Kitamura, Kazunori*; Nishi, Masataka

Fusion Science and Technology, 48(1), p.621 - 624, 2005/07

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

A new conceptual design of a tritium permeation test module assembly was developed for demonstration tests using a strong plasma source constructed in TPL for simulation of practical tritium permeation in the real plasma facing components and validation of the models and codes for evaluation of tritium permeation. The target module, to be irradiated by the high flux plasma beam, consists of a multi-layer structure of a plasma facing material plate and a copper substrate with pressurized coolant cavity. Tests using a preliminary model of the target module has been performed to verify thermal and mechanical behavior of the bonded structure and to assess its structural integrity focused on the bonded interface under the cyclic heat loads. After the heat load testing, no visible defect and crack was observed around the bonded interfaces with magnifying glass, and its structural integrity was verified. Also the first tests using tritium plasma at TSTA/LANL with the preliminary model was performed and process to measured tritium permeated was established.

JAEA Reports

Periodic safety review of the experimental fast reactor JOYO; Review of the activity for safety

Maeda, Yukimoto; Kashimura, Yoichi; Suzuki, Toshiaki; Isozaki, Kazunori; Hoshiba, Hideaki; Kitamura, Ryoichi; Nakano, Tomoyuki; Takamatsu, Misao; Sekine, Takashi

JNC-TN9440 2005-001, 540 Pages, 2005/02

JNC-TN9440-2005-001.pdf:8.35MB

Periodic safety review (Review of the activity for safety) which consisted of "Comprehensive evaluation of operation experience" and "Incorporation of the latest technical knowledge" was carried out up to January 2005.

JAEA Reports

Alternatives of ITER vacuum vessel support system

Omori, Junji*; Kitamura, Kazunori*; Araki, Masanori; Oono, Isamu*; Shoji, Teruaki

JAERI-Tech 2002-053, 86 Pages, 2002/07

JAERI-Tech-2002-053.pdf:3.81MB

no abstracts in English

Journal Articles

ITER engineering design

Shimomura, Yasuo; Tsunematsu, Toshihide; Yamamoto, Shin; Maruyama, So; Mizoguchi, Tadanori*; Takahashi, Yoshikazu; Yoshida, Kiyoshi; Kitamura, Kazunori*; Ioki, Kimihiro*; Inoue, Takashi; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 78(Suppl.), 224 Pages, 2002/01

no abstracts in English

Journal Articles

Key features of the ITER-FEAT magnet system

Okuno, Kiyoshi; Bessette, D.*; Ferrari, M.*; Huguet, M.*; Jong, C.*; Kitamura, Kazunori*; Krivchenkov, Y.*; Mitchell, N.*; Takigami, Hiroyuki*; Yoshida, Kiyoshi; et al.

Fusion Engineering and Design, 58-59, p.153 - 157, 2001/11

 Times Cited Count:2 Percentile:78.27

no abstracts in English

Journal Articles

Low cycle fatigue lifetime of HIP bonded Bi-metallic first wall structures of fusion reactors

Hatano, Toshihisa; Sato, Satoshi; Hashimoto, T.*; Kitamura, Kazunori*; Furuya, Kazuyuki; Kuroda, Toshimasa*; Enoeda, Mikio; Takatsu, Hideyuki

Journal of Nuclear Science and Technology, 35(10), p.705 - 711, 1998/10

 Times Cited Count:1 Percentile:83.53(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Analyses of divertor high heat-flux components on thermal and electromagnetic loads

Araki, Masanori; Kitamura, Kazunori*; Urata, Kazuhiro*; Suzuki, Satoshi

Fusion Engineering and Design, 42(1-4), p.381 - 387, 1998/09

 Times Cited Count:0 Percentile:100

no abstracts in English

Journal Articles

Dynamic analysis of the tokamak support system in ITER

*; Kitamura, Kazunori*; *; Koizumi, Koichi; Tada, Eisuke; Tsunematsu, Toshihide

Fusion Engineering and Design, 41, p.421 - 429, 1998/00

 Times Cited Count:3 Percentile:65.59

no abstracts in English

Journal Articles

High heat flux testing of a HIP bonded first wall panel with built-in circular cooling tubes

Hatano, Toshihisa; ; ; *; *; Kitamura, Kazunori*; Kuroda, Toshimasa*; Akiba, Masato; Takatsu, Hideyuki

Fusion Engineering and Design, 39-40, p.363 - 370, 1998/00

 Times Cited Count:20 Percentile:16.48

no abstracts in English

JAEA Reports

Design of ITER shielding blanket

Furuya, Kazuyuki; Sato, Satoshi; Hatano, Toshihisa; *; Kitamura, Kazunori*; Miura, H.*; *; Kuroda, Toshimasa*; Takatsu, Hideyuki

JAERI-Tech 97-022, 113 Pages, 1997/05

JAERI-Tech-97-022.pdf:3.42MB

no abstracts in English

Oral presentation

Preparation of procurement for ITER TF coil

Sugimoto, Makoto; Kitamura, Kazunori; Hamada, Kazuya; Nakajima, Hideo; Okuno, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Technology development and procurement plan for the winding pack of the ITER TF coil

Sugimoto, Makoto; Kitamura, Kazunori; Okuno, Kiyoshi

no journal, , 

no abstracts in English

Oral presentation

Fracture mechanics analysis of ITER toroidal field coil

Onodera, Osamu*; Iguchi, Masahide*; Saito, Masakatsu*; Hamada, Kazuya; Nakajima, Hideo; Okuno, Kiyoshi; Sugimoto, Makoto; Nakahira, Masataka; Kitamura, Kazunori; Takayanagi, Tadatoshi*; et al.

no journal, , 

no abstracts in English

Oral presentation

Buckling analysis of gravity support legs for JT-60SA vacuum vessel

Ejiri, Mitsuru*; Kitamura, Kazunori*; Araki, Takao*; Omori, Junji*; Asano, Shiro*; Hayakawa, Atsuro*; Shibama, Yusuke; Masaki, Kei; Sakasai, Akira

no journal, , 

In the operation of tokamak, such loads as electromagnetic and seismic are assumed to be imposed on the vacuum vessel (VV), and not a little thermal expansion takes place when VV is baked. The gravity support leg (GS) has to support the loads described above in addition to the dead weight of VV including in-vessel components and compensate deformation. The GS is equipped with plate spring (PS) to have both stiffness and flexibility. In this study, the buckling strength of the PSs was evaluated. The effect of the initial imperfection of the PSs which is assumed to result from machining or welding process on the buckling strength was also studied. It is concluded that GS has sufficient buckling strength against assumed initial imperfections.

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