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Ida, Mizuho; Nakamura, Hiroo; Sugimoto, Masayoshi
Fusion Engineering and Design, 82(15-24), p.2490 - 2496, 2007/10
Times Cited Count：11 Percentile：59.13(Nuclear Science & Technology)no abstracts in English
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：8 Percentile：49.22(Nuclear Science & Technology)no abstracts in English
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：22 Percentile：78.59(Nuclear Science & Technology)no abstracts in English
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：3 Percentile：24.41(Nuclear Science & Technology)no abstracts in English
TiO
in hydrogen atmosphereHoshino, 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：54 Percentile：94.40(Nuclear Science & Technology)no abstracts in English
O
-SiO Including CrPO
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：31 Percentile：86.40(Nuclear Science & Technology)no abstracts in English
Shimada, Katsuhiro; Ito, Junichi*; Matsukawa, Makoto; Kurihara, Kenichi
Fusion Engineering and Design, 82(5-14), p.1513 - 1518, 2007/10
Times Cited Count：3 Percentile：24.41(Nuclear Science & Technology)no abstracts in English
Nishimura, Arata*; Nishijima, Shigehiro*; Takeuchi, Takao*; Nishitani, Takeo
Fusion Engineering and Design, 82(5-14), p.1555 - 1560, 2007/10
Times Cited Count：6 Percentile：40.77(Nuclear Science & Technology)Recent researches on fusion reactor show neutron streaming from ports to outside of plasma vacuum vessels and neutron penetration through blanket and a neutron shielding structure. Therefore, superconducting magnet system in a fusion reactor will be irradiated by high energy particles. To evaluate the irradiation effect of fusion neutron on the superconducting magnet materials, a cryo-target system was constructed and installed at FNS/JAEA. The NbSn, NbAl samples and copper wires were cooled down to 4.5 K by a GM refrigerator and irradiation tests by 14 MeV neutron at cryogenic temperature were carried out. Change in electric resistance and critical temperatures were measured after irradiation. On the outside of the cryostat, GFRP and other sensors were arranged and irradiated at the same time. After the irradiation, the properties of those materials were investigated and the difference was discussed.
Kondo, Hiroo*; Kanemura, Takuji*; Yamaoka, Nobuo*; Miyamoto, Seiji*; Ida, Mizuho; Nakamura, Hiroo; Matsushita, Izuru*; Muroga, Takeo*; Horiike, Hiroshi*
Fusion Engineering and Design, 82(15-24), p.2483 - 2489, 2007/10
Times Cited Count：13 Percentile：63.96(Nuclear Science & Technology)Lithium flow experiments were conducted for International Fusion Materials Irradiation Facility (IFMIF) at Osaka University. In the experiment, Li plane jet of 10 mm in depth and 70 mm in width formed by a two contractions nozzle was tested in the velocity range of less than 15 m/s. In the present report, Li surface measurement by pattern projection method was tested. This is a three dimensional image measurement, where stripe patterns are projected onto the flow surface without touching it. The projected patterns were observed to be deformed according to the surface up- and- down. Three-dimensional surface shape could be obtained by analyzing the deformed patterns. By the method, shapes of wave pattern called surface wakes were successfully measured. The surface wakes were observed to be formed from the nozzle edge. It was found that the nozzle edge was damaged and became serrated after lithium flowing of 1,300 hours at this moment.
Kanemura, Takuji*; Kondo, Hiroo*; Yamaoka, Nobuo*; Miyamoto, Seiji*; Ida, Mizuho; Nakamura, Hiroo; Matsushita, Izuru*; Muroga, Takeo*; Horiike, Hiroshi*
Fusion Engineering and Design, 82(15-24), p.2550 - 2557, 2007/10
Times Cited Count：24 Percentile：80.95(Nuclear Science & Technology)For a study on characteristics of lithium target flow of International Fusion Materials Irradiation Facility (IFMIF), experiments were carried out by using a lithium loop at Osaka University. In the experiment, fluctuations of a free surface of the horizontal flow were directly measured by using an electro-contact probe acquiring condition of contact/non-contact of the probe with the flow surface as voltage data. Vertical location of the probe tip was set by 0.1 mm step. Horizontal location of the probe was 175 mm downstream from the nozzle exit, corresponding to the footprint of deuteron beam in the IFMIF case. It was found that the maximum amplitude of the surface wave, including rarely arising ones, was 2.2 mm at the center of the flow channel with width of 70 mm at the maximum flow velocity of 15 m/s. The average thickness of the flow was found to be 10.13 mm.
Batistoni, P.*; Angelone, M.*; Bettinali, L.*; Carconi, P.*; Fischer, U.*; Kodeli, I.*; Leichtle, D.*; Ochiai, Kentaro; Perel, R.*; Pillon, M.*; et al.
Fusion Engineering and Design, 82(15-24), p.2095 - 2104, 2007/10
Times Cited Count：30 Percentile：85.69(Nuclear Science & Technology)A neutronics experiment has been performed in the frame of European Fusion Technology Program on a mock-up of the EU Test Blanket Module (TBM), Helium Cooled Pebble Bed (HCPB) concept, with the objective to validate the capability of nuclear data to predict nuclear responses, such as the tritium production rate (TPR), with qualified uncertainties. In the experiment, the TPR has been measured using LiCO pellets at various depths at two symmetrical positions at each depth, one in the upper and one in the lower breeder cassette. Three independent measurements were performed by ENEA, TUD/VKTA and JAEA. The neutron flux in the beryllium layer was measured as well using activation foils.
Utin, Y.*; Ioki, Kimihiro; Alekseev, A.*; Bachmann, C.*; Cho, S. Y.*; Chuyanov, V.*; Jones, L.*; Kuzmin, E.*; Morimoto, Masaaki; Nakahira, Masataka; et al.
Fusion Engineering and Design, 82(15-24), p.2040 - 2046, 2007/10
Times Cited Count：2 Percentile：17.90(Nuclear Science & Technology)Recent progress of the ITER vacuum vessel (VV) design is presented. As the ITER construction phase approaches, the VV design has been improved and developed in more detail with the focus on better performance, improved manufacture and reduced cost. Based on achievements of manufacturing studies, design improvement of the typical VV sector (#1) has been nearly finalized. Design improvement of other sectors is in progress - in particular, of the VV sector #2 and #3 which interface with the ports for the neutral beam injection. For all sectors, the concept for the in-wall shielding has progressed and developed in more detail. The design progress of the VV sectors has been accompanied by the progress of the port structures. In particular, design of the NB Ports was advanced with the focus on the heat-flux components to handle the heat input of the neutral beams. Structural analyses have been performed to validate all design improvements.
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：35.61(Nuclear Science & Technology)no abstracts in English
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：8 Percentile：49.22(Nuclear Science & Technology)no abstracts in English
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：35.61(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.
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：17.90(Nuclear Science & Technology)no abstracts in English
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：5 Percentile：35.61(Nuclear Science & Technology)no abstracts in English
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：17.90(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.
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：35.61(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.
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：5 Percentile：35.61(Nuclear Science & Technology)no abstracts in English
