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Yamada, Hirokazu*; Nagao, Yoshiharu; Kawamura, Hiroshi; Nakao, Makoto*; Uchida, Munenori*; Ito, Haruhiko
Fusion Engineering and Design, 69(1-4), p.269 - 273, 2003/09
Times Cited Count：14 Percentile：66.94(Nuclear Science & Technology)no abstracts in English
Takahashi, Koji; Ishitsuka, Etsuo; Moeller, C. P.*; Hayashida, Kazunori*; Kasugai, Atsushi; Sakamoto, Keishi; Hayashi, Kenichi*; Imai, Tsuyoshi
Fusion Engineering and Design, 66-68, p.473 - 479, 2003/09
Times Cited Count：11 Percentile：59.38(Nuclear Science & Technology)For the purpose to confirm the reliability of the front steering concept, tests of the front steering launcher mock-up and neutron irradiation tests of bearings for a movable mirror were carried out under the ITER conditions. The max. stress of the flexible pipes for the movable mirror was measuerd to be 60MPa, much less than the allowable stress and agree with the calculation. No degradation on the performance of bearings was obtained for the assumed fluence of ITER. The mock-up of remote steering(RS) launcher was tested and RF radiation of 0.5MW-3sec and 0.2MW-10sec over 0-10
were performed. No degradation was obseved, either. The new launcher which has the capability of wider range rf beam steering and the corrugated square waveguide with four miter bends that yield the dog-legged structure has been designed, based on the test results. It has been fabricating for high power experiments.
Inoue, Takashi; Hanada, Masaya; Iga, Takashi*; Imai, Tsuyoshi; Kashiwagi, Mieko; Kawai, Mikito; Morishita, Takatoshi; Taniguchi, Masaki; Umeda, Naotaka; Watanabe, Kazuhiro; et al.
Fusion Engineering and Design, 66-68, p.597 - 602, 2003/09
Times Cited Count：21 Percentile：78.49(Nuclear Science & Technology)The neutral beam (NB) injection has been one of the most promising methods for plasma heating and current drive in tokamak fusion devices. JAERI has developed high energy electrostatic accelerators for the NB systems in JT-60U and ITER. Recent progress on this R&D are as follows: 1) In the JT-60U NB system, some of the beams has been deflected due to distorted electric field in the accelerator, resulting in an excess heat load on the NB port. By correcting the electric field, a continuous injection of H
beam was succeeded for 10 s with the NB power of 2.6 MW at 355 keV. 2) To increase the beam energy, a metal structure called stress ring was designed. The ring reduces electric field concentration at the triple junction point (interface between metal and dielectric insulator inside vacuum). Initial test of the accelerators with the stress rings has shown higher voltage hold off performance in both accelerators for JT-60U and ITER R&D than that without rings.
Yoshida, Shigeo*; Nishitani, Takeo; Ochiai, Kentaro; Kaneko, Junichi*; Hori, Junichi; Sato, Satoshi; Yamauchi, Michinori*; Tanaka, Ryohei*; Nakao, Makoto*; Wada, Masayuki*; et al.
Fusion Engineering and Design, 69(1-4), p.637 - 641, 2003/09
Times Cited Count：9 Percentile：53.35(Nuclear Science & Technology)no abstracts in English
Morimoto, Yuichi*; Ochiai, Kentaro; Sato, Satoshi; Hori, Junichi; Yamauchi, Michinori*; Nishitani, Takeo
Fusion Engineering and Design, 69(1-4), p.643 - 648, 2003/09
Times Cited Count：4 Percentile：31.64(Nuclear Science & Technology)no abstracts in English
Furuya, Kazuyuki; Wakai, Eiichi; Ando, Masami; Sawai, Tomotsugu; Iwabuchi, Akira*; Nakamura, Kazuyuki; Takeuchi, Hiroshi
Fusion Engineering and Design, 69(1-4), p.385 - 389, 2003/09
Times Cited Count：23 Percentile：80.7(Nuclear Science & Technology)In a fusion reactor, a blanket made of a low activation material like F82H is fabricated by solid Hot Isostatic pressing (HIP) joining method. In a previous study, blanket, grain coarsenings were found in a mock-up around HIP-joined region. To verify an effect of the coarsenings on a strength of the HIP-joined region, tensile test and hardness measurement were done. As the results, the tensile strength increased by about 50 MPa, and the elongation decreased by about 4 % in comparison with that of a standard alloy. Though the hardness was almost constant both in the coarsening and a non-coarsening regions, both of these hardness increased by about 5 %. Therefore, it could be judged that change of the tensile property is due to increase of the hardness. On the other hand, tensile and impact tests of a base metal without coarsening resulted in DBTT increase by about 40 K, although the tensile property was nearly equal to that of the joined-region with coarsening. It can be understood that this is the effect of the heat treatments in the fabrication process of the mock-up.
Ti and Li
TiO
Nakamichi, Masaru; Kawamura, Hiroshi; Uchida, Munenori*
Fusion Engineering and Design, 69(1-4), p.257 - 261, 2003/09
Times Cited Count：9 Percentile：49.89(Nuclear Science & Technology)no abstracts in English
TiUchida, Munenori*; Ishitsuka, Etsuo; Kawamura, Hiroshi
Fusion Engineering and Design, 69(1-4), p.499 - 503, 2003/09
Times Cited Count：26 Percentile：82.89(Nuclear Science & Technology)no abstracts in English
Uchida, Munenori*; Kawamura, Hiroshi; Uda, Minoru*; Ito, Yoshio*
Fusion Engineering and Design, 69(1-4), p.491 - 498, 2003/09
Times Cited Count：15 Percentile：69.06(Nuclear Science & Technology)no abstracts in English
Onozuka, Masanori*; Takeda, Nobukazu; Nakahira, Masataka; Shimizu, Katsusuke*; Nakamura, Tomomichi*
Fusion Engineering and Design, 69(1-4), p.757 - 762, 2003/09
Times Cited Count：2 Percentile：19(Nuclear Science & Technology)The dynamic behavior of the ITER tokamak assembly has been investigated. Three experimental models have been considered to validate the numerical analysis methods for the dynamic events, mainly seismic events. A 1/8-scaled tokamak model, which is based on the 1998 ITER design, is under construction. Non-linear vibration characteristics, such as damping, can only be identified by a full-scale model. Therefore, a full-scale gravity support structure for the coil system has been designed and will be tested. In addition, for the sub-scaled tokamak model, the VV is assumed to be a rigid structure. This assumption is to be verified using a 1/20-scaled model. The above experimental models and their testing conditions have analytically and numerically evaluated. For example, both the static and dynamic spring constants obtained by static analysis and eigen-value analysis, respectively, were evaluated to be in good agreement.
TiO
pebble bed under neutron irradiationKawamura, Hiroshi; Kikukawa, Akihiro*; Tsuchiya, Kunihiko; Yamada, Hirokazu*; Nakamichi, Masaru; Ishitsuka, Etsuo; Enoeda, Mikio; Ito, Haruhiko
Fusion Engineering and Design, 69(1-4), p.263 - 267, 2003/09
Times Cited Count：3 Percentile：25.79(Nuclear Science & Technology)no abstracts in English
on the reduction of lithium titanate induced by H in the sweep gasTsuchiya, Kunihiko; Alvani, C.*; Kawamura, Hiroshi; Yamada, Hirokazu*; Casado, S.*; Contini, V.*
Fusion Engineering and Design, 69(1-4), p.443 - 447, 2003/09
Times Cited Count：4 Percentile：31.64(Nuclear Science & Technology)no abstracts in English
TiO pebbles fabricated by direct-wet processTsuchiya, Kunihiko; Kawamura, Hiroshi; Uchida, Munenori*; Casado, S.*; Alvani, C.*; Ito, Yoshio*
Fusion Engineering and Design, 69(1-4), p.449 - 453, 2003/09
Times Cited Count：19 Percentile：75.79(Nuclear Science & Technology)no abstracts in English
Yamamoto, Takumi; JT-60 Team
Fusion Engineering and Design, 66-68, p.39 - 48, 2003/09
Times Cited Count：3 Percentile：25.79(Nuclear Science & Technology)Development of technology on facilities for JT-60U and resultant progress of the plasma performance are reported. The main objectives of JT-60U are to demonstrate integrated high plasma performance that contributes to establishment of the physical and technological bases of ITER and a steady state tokamak fusion reactor. Recently, performance exploration in advanced tokamak regimes has been conducted intensively, by using 500 keV negative-ion based neutral beam injection (N-NBI) and 110GHz electron cyclotron (EC) systems for plasma heating and current drive, and a repetitive centrifugal pellet injector for efficient core particle fueling.
Konishi, Satoshi; Okano, Kunihiko*; Tokimatsu, Koji*; Ito, Keishiro*; Ogawa, Yuichi*
Fusion Engineering and Design, 69(1-4), p.523 - 529, 2003/09
Times Cited Count：4 Percentile：31.64(Nuclear Science & Technology)no abstracts in English
Matsukawa, Makoto; Ishida, Shinichi; Sakasai, Akira; Urata, Kazuhiro*; Senda, Ikuo*; Kurita, Genichi; Tamai, Hiroshi; Sakurai, Shinji; Miura, Yushi; Masaki, Kei; et al.
Fusion Engineering and Design, 66-68(1-4), p.703 - 708, 2003/09
Times Cited Count：2 Percentile：19(Nuclear Science & Technology)no abstracts in English
Ando, Toshinari*; Kikuchi, Mitsuru
Fusion Engineering and Design, 66-68, p.1097 - 1102, 2003/09
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)In order to realize a low cost TF superconducting coil system for tokamak fusion reactors, the design of TF superconducting coil with a copper coil in place of pure copper wires within cable-in-conduit conductors is considered, which are needed for the thermal protection. This consideration is carried out under the condition that hot spot temperature of conductor is less than 250 K and a plasma-confinement vacuum vessel has no damage during the TF coil fast discharge in the ITER TF coil design. As the result, it is found that the conductor area is reduced by 35 % and the copper coil is installed into the original coil case together with a TF coil winding. An external resister system is reduced by around 40 % of the original system because 40 % of magnetic energy (40 GJ) stored in the ITER TF coil is dissipated into the copper coil during the fast discharge.
Laesser, R.*; Gruenhagen, S.*; Kawamura, Yoshinori
Fusion Engineering and Design, 69(1-4), p.813 - 817, 2003/09
Times Cited Count：15 Percentile：69.06(Nuclear Science & Technology)Various analytical techniques exist to determine the compositions of gases handled in the fuel cycle of future fusion machines. Gas chromatography was found to be the most appropriate method. The main disadvantages of conventional gas chromatography were the long retention times for the heavy hydrogen species of more than half an hour. Recent progress in the development of micro-gas chromatography has reduced these retention times to approximately 3 minutes. The usefulness of micro-gas chromatography for the analysis of hydrogen and impurity gas mixtures in the fuel cycle of future fusion machines is presented and the advantages and draw backs are discussed.
Morimoto, Yasutomi*; Sasaki, Masayoshi*; Kimura, Hiromi*; Sakamoto, Keishi; Imai, Tsuyoshi; Okuno, Kenji*
Fusion Engineering and Design, 66-68, p.651 - 656, 2003/09
Times Cited Count：3 Percentile：25.79(Nuclear Science & Technology)no abstracts in English
Nakamura, Hiroo; Burgazzi, L.*; Cevolani, S.*; Dell'Ocro, G.*; Fazio, C.*; Giusti, D.*; Horiike, Hiroshi*; Ida, Mizuho*; Kakui, Hideo*; Loginov, N.*; et al.
Journal of Nuclear Materials, 307-311(Part.2), p.1675 - 1679, 2002/12
Times Cited Count：4 Percentile：29.25(Materials Science, Multidisciplinary)This paper describes the latest design of the IFMIF liquid Li target system reflecting the KEP results. Future prospects will be also summarized. To handle an averaged heat flux of 1 GW/m2 under a continuous 10 MW D beam deposition, a high-speed Li flow of 20 m/s, a double reducer nozzle and a concaved flow are applied to the target design. Hydraulic characteristics of the Li target design have been validated in a water jet experiment. To obtain a control scenario of the Li loop in an accident of the D beam trip, a transient analysis has been done. To control tritium and impurities in Li, a cold trap and two kinds of hot trap are adopted in Li purification loop. To maintain reliable continuous operation, various diagnostics are attached to the target assembly. To exchange the target assembly and back wall, a remote handling system with a multi axis arm and welding/cutting tool are designed. As an option, design of a replaceable back wall with a mechanical seal is being in progress. In a next phase of IFMIF beyond 2004, a Li test loop will be constructed for engineering validation.
