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Journal Articles

Estimation and control of beryllium-7 behavior in liquid lithium loop of IFMIF

Ida, Mizuho; Nakamura, Hiroo; Sugimoto, Masayoshi

Fusion Engineering and Design, 82(15-24), p.2490 - 2496, 2007/10

 Times Cited Count:4 Percentile:33.11(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of optimum manufacturing technologies of radial plates for the ITER toroidal field coils

Nakajima, Hideo; Hamada, Kazuya; Okuno, Kiyoshi; Abe, Kanako*; Shimizu, Tatsuya; Kakui, Hideo*; Yamaoka, Hiroto*; Maruyama, Naoyuki*; Takayanagi, Tadatoshi*

Fusion Engineering and Design, 82(5-14), p.1473 - 1480, 2007/10

 Times Cited Count:5 Percentile:39.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Demonstration of full scale JJ1 and 316LN fabrication for ITER TF coil structure

Hamada, Kazuya; Nakajima, Hideo; Kawano, Katsumi; Takano, Katsutoshi; Tsutsumi, Fumiaki; Okuno, Kiyoshi

Fusion Engineering and Design, 82(5-14), p.1481 - 1486, 2007/10

 Times Cited Count:12 Percentile:66.47(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Basic analysis of weldability and machinability of structural materials for ITER toroidal field coils

Onozuka, Masanori*; Shimizu, Katsusuke*; Urata, Kazuhiro*; Kimura, Masahiro*; Kadowaki, Hirokazu*; Okamoto, Mamoru*; Nakajima, Hideo; Hamada, Kazuya; Okuno, Kiyoshi

Fusion Engineering and Design, 82(5-14), p.1431 - 1436, 2007/10

 Times Cited Count:2 Percentile:19.85(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Non-stoichiometory and vaporization characteristic of Li$$_{2.1}$$TiO$$_{3.05}$$ in hydrogen atmosphere

Hoshino, Tsuyoshi; Yasumoto, Masaru*; Tsuchiya, Kunihiko; Hayashi, Kimio; Nishimura, Hidetoshi*; Suzuki, Akihiro*; Terai, Takayuki*

Fusion Engineering and Design, 82(15-24), p.2269 - 2273, 2007/10

 Times Cited Count:41 Percentile:93.5(Nuclear Science & Technology)

no abstracts in English

Journal Articles

In-pile tritium permeation through F82H steel with and without a ceramic coating of Cr$$_{2}$$O$$_{3}$$-SiO$$_{2}$$ Including CrPO$$_{4}$$

Nakamichi, Masaru; Kulsartov, T. V.*; Hayashi, Kimio; Afanasyev, S. E.*; Shestakov, V. P.*; Chikhray, Y. V.*; Kenzhin, E. A.*; Kolbaenkov, A. N.*

Fusion Engineering and Design, 82(15-24), p.2246 - 2251, 2007/10

 Times Cited Count:24 Percentile:83.86(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Design of a lip seal-replaceable backwall for IFMIF liquid lithium target

Nakamura, Hiroo; Ida, Mizuho; Chida, Teruo; Furuya, Kazuyuki*; Sugimoto, Masayoshi

Fusion Engineering and Design, 82(15-24), p.2671 - 2676, 2007/10

 Times Cited Count:5 Percentile:39.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Development of beam source and bushing for ITER NB system

Inoue, Takashi; Hanada, Masaya; Kashiwagi, Mieko; Taniguchi, Masaki; Tobari, Hiroyuki; Dairaku, Masayuki; Umeda, Naotaka; Watanabe, Kazuhiro; Sakamoto, Keishi; Ikeda, Yoshitaka

Fusion Engineering and Design, 82(5-14), p.813 - 818, 2007/10

 Times Cited Count:7 Percentile:49.85(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Demonstration tests for manufacturing the ITER vacuum vessel

Shimizu, Katsusuke*; Onozuka, Masanori*; Usui, Yukinori*; Urata, Kazuhiro*; Tsujita, Yoshihiro*; Nakahira, Masataka; Takeda, Nobukazu; Kakudate, Satoshi; Omori, Junji; Shibanuma, Kiyoshi

Fusion Engineering and Design, 82(15-24), p.2081 - 2088, 2007/10

 Times Cited Count:5 Percentile:39.35(Nuclear Science & Technology)

To confirm the manufacturing and assembly process of the ITER vacuum vessel (VV), a series of related tests has been conducted. (1) Using a full-scale partial mock-up, fabrication methods are to be examined to determine feasibility. (2) To simulate a series of field-joint assembly operations, a test stand was built. (3) To provide an appropriate shield gas supply on the back side of the outer shell during field-joint welding, three types of back-seal structures have been tested. (4) The applicability of UT methods for volumetric inspection has been investigated. (5) Applicability of Liquid Penetrant Testing as a surface examination for the VV interior surface (i.e. ultra-vacuum side) has been investigated.

Journal Articles

Prospective performances in JT-60SA towards the ITER and DEMO relevant plasmas

Tamai, Hiroshi; Fujita, Takaaki; Kikuchi, Mitsuru; Kizu, Kaname; Kurita, Genichi; Masaki, Kei; Matsukawa, Makoto; Miura, Yukitoshi; Sakurai, Shinji; Sukegawa, Atsuhiko; et al.

Fusion Engineering and Design, 82(5-14), p.541 - 547, 2007/10

 Times Cited Count:9 Percentile:57.83(Nuclear Science & Technology)

JT-60SA is positioned as the ITER satellite tokamak to conduct research elements to support and supplement ITER towards DEMO under the joint collaboration of Japan and EU. After the discussions in JA-EU Satellite Tokamak Working Group in 2005, the heating power is increased up to 41MW, 100s to ensure the ITER support research. With such increased heating power, the prospective plasma performances are analysed by the equilibrium and transport analysis codes. Operation window of a fully non-inductive current drive is extended to high density region. Simultaneous achievement of high equivalent Q$$_{DT}$$ and high normalised beta is also expected in wide operational margin. Those prospects strongly indicate that JT-60SA is suitable machine to conduct the advanced research orienting to ITER and DEMO.

Journal Articles

Verification of nuclear data for DT neutron induced charged-particle emission reaction of light nuclei

Kondo, Keitaro; Murata, Isao*; Ochiai, Kentaro; Kubota, Naoyoshi; Miyamaru, Hiroyuki*; Takagi, Satoshi*; Shido, Shoichi*; Konno, Chikara; Nishitani, Takeo

Fusion Engineering and Design, 82(15-24), p.2786 - 2793, 2007/10

 Times Cited Count:2 Percentile:19.85(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Six-party qualification program of FW fabrication methods for ITER blanket module procurement

Ioki, Kimihiro; Elio, F.*; Barabash, V.*; Chuyanov, V.*; Rozov, V.*; Wang, X.*; Chen, J.*; Wang, L.*; Lorenzetto, P.*; Peacock, A.*; et al.

Fusion Engineering and Design, 82(15-24), p.1774 - 1780, 2007/10

 Times Cited Count:13 Percentile:69.08(Nuclear Science & Technology)

In December 2005, the new procurement allocation plan of the ITER components among the seven Parties was prepared. The need to qualify for procurement of the specific components was especially introduced in the document. The main features and milestones of the qualification program are described in "Procurement Plan" for each specific component. Due to the complicated features of FW procurement, the procurement document has to be developed precisely. To guarantee high quality of 1700 FW panels produced by 6 different Parties, a qualification program is essential. The qualification mock-up is 80 mm wide, 240 mm long and 81 mm thick with 3 beryllium tiles 10 mm thick. Heat load tests will be performed on the qualification mock-ups in 2007 in EU and USA facilities. The maximum design heat load on the ITER FW is 0.5 MW/m $$^{2}$$ (steady state) $$times$$ 30,000 shots. Mechanical tests of joints are also required using standardized methods. Only Parties which have satisfied the acceptance criteria of the qualification tests can proceed to the procurement stage of the ITER FW. Semi-prototypes (roughly 1000 mm $$times$$ 200 mm) are also requested before the ITER FW manufacturing.

Journal Articles

Improvement of data processing system for advanced diagnostics in JT-60U

Oshima, Takayuki; Kiyono, Kimihiro; Sakata, Shinya; Sato, Minoru; Totsuka, Toshiyuki; Iba, Katsuyuki*; Ozeki, Takahisa; Hirayama, Toshio

Fusion Engineering and Design, 82(5-14), p.1210 - 1215, 2007/10

 Times Cited Count:2 Percentile:19.85(Nuclear Science & Technology)

In JT-60U the data processing system, providing the data acquisition, producing the diagnostic data base, and communicating with the JT-60U control system. The MSP-ISP was replaced by a new Inter-Shot Processor based on the UNIX-OS of a workstation (UNIX-ISP) in 2005. The performance of UNIX-ISP is 2 times as high as that of the MSP-ISP in a stand-alone test using the data conversion program of the CXRS data. Thus we can expect the reduction of the processing time by the optimization of the total sequence. For the remote experiment, we have developed a system called RMSVR with which we can set discharge parameters from the remote site, and thereby the consistency of input parameters is checked. The high security of the remote experiment system is established by the certification and the encrypted communication based on ITBL. A verification test between a university and JAEA Naka indicates that the system using the HTTPS protocol is suitable for the remote experiment.

Journal Articles

Design of the superconducting coil system in JT-60SA

Tsuchiya, Katsuhiko; Kizu, Kaname; Ando, Toshinari*; Tamai, Hiroshi; Matsukawa, Makoto

Fusion Engineering and Design, 82(5-14), p.1519 - 1525, 2007/10

 Times Cited Count:4 Percentile:33.11(Nuclear Science & Technology)

no abstracts in English

Journal Articles

The Plasma movie database system for JT-60

Sueoka, Michiharu; Kawamata, Yoichi; Kurihara, Kenichi; Seki, Akiyuki

Fusion Engineering and Design, 82(5-14), p.1008 - 1014, 2007/10

 Times Cited Count:2 Percentile:19.85(Nuclear Science & Technology)

A plasma movie is generally expected as one of the most efficient methods to know what plasma discharge has been conducted in the experiment. On this motivation we have developed and operated a real-time plasma shape visualization system over ten years. The current plasma movie is composed of (1) video camera picture looking at a plasma, (2) computer graphic (CG) picture, and (3) magnetic probe signal as a sound channel. In order to use this movie efficiently, we have developed a new plasma movie database system, where a plasma movie is available (downloadable) for experiment data analyses at the Web-site. This new system and its future prospects will be discussed in detals from a technological point of view.

Journal Articles

Thin slit streaming experiment for ITER by using D-T neutron source

Ochiai, Kentaro; Sato, Satoshi; Wada, Masayuki*; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori; Abe, Yuichi; Nishitani, Takeo; Konno, Chikara

Fusion Engineering and Design, 82(15-24), p.2794 - 2798, 2007/10

 Times Cited Count:5 Percentile:39.35(Nuclear Science & Technology)

Neutron streaming experiments have been conducted by using the FNS D-T neutron source at Japan Atomic Energy Agency under the ITER/ITA Task 73-10 in order to evaluate effects of the slit on nuclear properties and validate prediction accuracies on numerical simulations. The experimental assembly with a slit of 2 cm in width and 55 cm in depth was prepared with two iron blocks of 30 cm in height, 100 cm in width and 55cm in thickness as first campaign. The slit was located in the 12-cm upper part from the D-T neutron source point. In order to evaluate distributions of the neutron fluxes along the slit as a function of the depth from the assembly surface, fission reaction rates were measured by U-238 and U-235 micro-fission chambers. The experimental accuracies of these fission reaction rates are within 5%. Monte-Carlo calculation code, MCNP-4c, was used to calculate the U-238 and U-235 reaction rates and neutron energy spectra due to each measured position. From our first experiment, the following facts were found: (1) At d = 20 and 40 cm, reaction rates on U-238, which represent fast neutron flux, decreased by about three orders of magnitude along slits with 50 cm in depth. Monte Carlo calculation results agree well with measured values within 6 %. (2) Reaction rates on U-235, which represent thermal neutron flux, decrease by about one order of magnitude along slits with 50 cm in depth. Values of C/E of U-238 and U-235 reaction rates were 1.10-1.22 and 1.10-1.23 respectively and the calculated values overestimated slightly.

Journal Articles

Engineering design of the ITER invessel neutron monitor using micro-fission chambers

Nishitani, Takeo; Yamauchi, Michinori; Izumi, Mikio*; Hayakawa, Atsuro*; Ebisawa, Katsuyuki*; Kondoh, Takashi; Kusama, Yoshinori

Fusion Engineering and Design, 82(5-14), p.1192 - 1197, 2007/10

 Times Cited Count:4 Percentile:33.11(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Evaluation of bending strain dependence of critical current of Nb$$_{3}$$Al conductor for coils with react-and-wind method

Kizu, Kaname; Tsuchiya, Katsuhiko; Shimada, Katsuhiro; Ando, Toshinari*; Hishinuma, Yoshimitsu*; Koizumi, Norikiyo; Matsukawa, Makoto; Miura, Yushi*; Nishimura, Arata*; Okuno, Kiyoshi; et al.

Fusion Engineering and Design, 82(5-14), p.1493 - 1499, 2007/10

 Times Cited Count:3 Percentile:26.87(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Measurement of thermal expansion of Li$$_2$$TiO$$_3$$ pebble bed

Tanigawa, Hisashi; Enoeda, Mikio; Akiba, Masato

Fusion Engineering and Design, 82(15-24), p.2259 - 2263, 2007/10

 Times Cited Count:9 Percentile:57.83(Nuclear Science & Technology)

In order to analyze thermo-mechanical behaviour of a Li$$_2$$TiO$$_3$$ pebble bed in the breeding blanket, thermal expansion of the bed was measured. For the bed with packing sates corresponding to the current design, there is no correlation between the expansion and the packing factor.

Journal Articles

Technical design of NBI system for JT-60SA

Ikeda, Yoshitaka; Akino, Noboru; Ebisawa, Noboru; Hanada, Masaya; Inoue, Takashi; Honda, Atsushi; Kamada, Masaki; Kawai, Mikito; Kazawa, Minoru; Kikuchi, Katsumi; et al.

Fusion Engineering and Design, 82(5-14), p.791 - 797, 2007/10

 Times Cited Count:19 Percentile:79.3(Nuclear Science & Technology)

Modification of JT-60U to a superconducting device (so called JT-60SA) has been planned to contribute to ITER and DEMO. The NBI system is required to inject 34 MW for 100 s. The upgraded NBI system consists of twelve positive ion based NBI (P-NBI) units and one negative ion based NBI (N-NBI) unit. The injection power of the P-NBI units are 2 MW each at 85 keV, and the N-NBI unit will be 10 MW at 500 keV, respectively. On JT-60U, the long pulse operation of 30 s at 2 MW (85 keV) and 20 s at 3.2 MW (320 keV) have been achieved on P-NBI and N-NBI units, respectively. Since the temperature increase of the cooling water in both ion sources is saturated within 20 s, further pulse extension up to 100 s is expected to mainly modify the power supply systems in addition to modification of the N-NBI ion source for high acceleration voltage. The detailed technical design of the NBI system for JT-60SA is presented.

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