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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：53.35(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
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.
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：36.18(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：36.18(Nuclear Science & Technology)no abstracts in English
TiO
pebble bedTanigawa, Hisashi; Enoeda, Mikio; Akiba, Masato
Fusion Engineering and Design, 82(15-24), p.2259 - 2263, 2007/10
Times Cited Count：10 Percentile：56.84(Nuclear Science & Technology)In order to analyze thermo-mechanical behaviour of a LiTiO 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.
Ida, Mizuho; Nakamura, Hiroo; Sugimoto, Masayoshi
Fusion Engineering and Design, 82(15-24), p.2490 - 2496, 2007/10
Times Cited Count：7 Percentile：45.97(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：49.99(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：79.41(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：2 Percentile：18.25(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：94.66(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：27 Percentile：83.24(Nuclear Science & Technology)no abstracts in English
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：18.25(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：36.18(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：18.25(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.
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：26 Percentile：83.24(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.
Sakurai, Shinji; Masaki, Kei; Shibama, Yusuke; Tamai, Hiroshi; Matsukawa, Makoto
Fusion Engineering and Design, 82(15-24), p.1767 - 1773, 2007/10
Times Cited Count：10 Percentile：56.84(Nuclear Science & Technology)The Japanese national project toward DEMO reactor and a satellite tokamak project for ITER in a Broader Approach with Japan and EU collaboration are combined as the JT-60SA (Super Advanced) project. Design of PFC for JT-60SA is widely modified from original national plan due to the increase of plasma heating power and annual neutron yield. Mono-block divertor target aiming at power handling of 15 MW/m
should be adopted to an outer divertor, because expected heat flux will exceed 10 MW/m. Since high coolant flow velocity of 10-12 m/s is required to enhance heat transfer and critical heat flux for swirl or screw tube, primary coolant water system is increased from 1300 to 4600 m
/h. Remote handling system similar with ITER blanket manipulator is adopted to maintain plasma-facing components. Divertor cassette has 10 degree width in toroidal direction and weight of 300 kg itself due to the limitation of port width and manipulator.
Tsuru, Daigo; Enoeda, Mikio; Akiba, Masato
Fusion Engineering and Design, 82(15-24), p.2274 - 2281, 2007/10
Times Cited Count：4 Percentile：30.34(Nuclear Science & Technology)In the safety design and technology of blankets for the Fusion DEMO reactor developed in Japan, coolant ingress in the blanket box structure is one of the most important events. Especially the thermal hydraulics in the pebble bed in the case of the high pressure coolant ingress is very important to evaluate the pressure propagation and coolant flow behavior. This paper presents the preliminary results of the pressure loss characteristics by the coolant ingress in the pebble bed. Experiments have been performed to simulate the helium coolant ingress into breeder and multiplier pebble beds and to evaluate the pressure loss in the pebble beds. The measured pressure losses are compared with the predicted values by Ergun's equation, which is the correlation equation on pressure loss of the flow through porous medium. The experimental results are discussed to identify the effect of constraint of pebble bed on the pressure relief performance of the pebble bed type solid breeder blanket.
Shimomura, Koji*; Takenaga, Hidenobu; Tsutsui, Hiroaki*; Mimata, Hideyuki*; Iio, Shunji*; Miura, Yukitoshi; Tani, Keiji; Kubo, Hirotaka; Sakamoto, Yoshiteru; Hiratsuka, Hajime; et al.
Fusion Engineering and Design, 82(5-14), p.953 - 960, 2007/10
Times Cited Count：3 Percentile：24.69(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：24.69(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：41.42(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.
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：27 Percentile：83.96(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.
