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Wakai, Eiichi; Kondo, Hiroo; Kanemura, Takuji; Hirakawa, Yasushi; Furukawa, Tomohiro; Hoashi, Eiji*; Fukada, Satoshi*; Suzuki, Akihiro*; Yagi, Juro*; Tsuji, Yoshiyuki*; et al.
Proceedings of Plasma Conference 2014 (PLASMA 2014) (CD-ROM), 2 Pages, 2014/11
In the IFMIF/EVEDA (International Fusion Materials Irradiation Facility/ Engineering Validation and Engineering Design Activity), the validation tests of the EVEDA lithium test loop with the world's highest flow rate of 3000 L/min was succeeded in generating a 100 mm-wide and 25 mm-thick free-surface lithium flow steadily under the IFMIF operation condition of a high-speed of 15 m/s at 250
C in a vacuum of 10 
Pa. Some excellent results of the recent engineering validations including lithium purification, lithium safety, and remote handling technique were obtained, and the engineering design of lithium facility was also evaluated. These results will advance greatly the development of an accelerator-based neutron source to simulate the fusion reactor materials irradiation environment as an important key technology for the development of fusion reactor materials.
Sato, Satoshi; Iida, Hiromasa*; Tanigawa, Hisashi; Hirose, Takanori; Ochiai, Kentaro; Konno, Chikara; Enoeda, Mikio
no journal, ,
Shielding analyses have been performed on the ITER/TBM and its port by using Monte Carlo radiation transport calculation code MCNP and activation calculation code ACT-4. CAD data were automatically converted to MCNP data on the TBM, shield, pipes and bio-shield by the CAD/MCNP conversion code, and their MCNP data have been inserted to the ITER 40 degree model. We evaluated the effective dose rate in operation, nuclear heating, tritium production rate, effective dose rate after shutdown and induced activity.
Tsuru, Daigo; Sakurai, Shinji; Nakamura, Shigetoshi; Ozaki, Hidetsugu; Seki, Yohji; Yokoyama, Kenji; Suzuki, Satoshi
no journal, ,
no abstracts in English
Shibama, Yusuke; Okano, Fuminori; Yagyu, Junichi; Kaminaga, Atsushi; Miyo, Yasuhiko; Hayakawa, Atsuro*; Sagawa, Keiich*; Mochida, Tsutomu*; Morimoto, Tamotsu*; Hamada, Takashi*; et al.
no journal, ,
no abstracts in English
Imazawa, Ryota; Ono, Takehiro; Kawano, Yasunori; Itami, Kiyoshi
no journal, ,
no abstracts in English
Ogawa, Hiroaki; Kitazawa, Sin-iti; Sugie, Tatsuo; Katsunuma, Atsushi*; Kitazawa, Daisuke*; Omori, Keisuke*; Itami, Kiyoshi
no journal, ,
no abstracts in English
Honda, Mitsuru; Satake, Shinsuke*; Suzuki, Yasuhiro*; Yoshida, Maiko; Hayashi, Nobuhiko; Kamiya, Kensaku; Matsuyama, Akinobu; Shinohara, Koji; Matsunaga, Go; Nakata, Motoki; et al.
no journal, ,
no abstracts in English
Yamamoto, Tsuyoshi; Hatae, Takaki; Yatsuka, Eiichi; Sugie, Tatsuo; Ogawa, Hiroaki; Takeuchi, Masaki; Kitazawa, Sin-iti; Ota, Kazuya*; Hashimoto, Yasunori*; Nakamura, Kitaru*; et al.
no journal, ,
no abstracts in English
Yoshida, Masafumi; Hanada, Masaya; Kojima, Atsushi; Kashiwagi, Mieko; Umeda, Naotaka; Hiratsuka, Junichi; Akino, Noboru; Endo, Yasuei; Komata, Masao; Mogaki, Kazuhiko; et al.
no journal, ,
One of the key issues for producing high current beams in JT-60SA is a uniform production of the negative ions over the large ion extraction area. Non-uniformity of the negative ion beams in the JT-60 negative ion source was improved by modifying the magnetic filter in the source from the PG filter to a tent-shaped filter. In this work, in order to clarify the influence of the magnetic filter modification on arc efficiency and co-electron current is investigated by means of measurements of H ion, H atoms, co-electron current and beam intensity. As a result, the arc efficiency increase due to increase of H ions and H atoms by reduction of filter field. Although the higher electrons current was extracted than the original PG filter, the co-extracted electron could be suppressed by optimization of the bias voltage. This result contributes to extend the pulse duration time up to 100 s for JT-60SA.
Miyata, Yoshiaki; Suzuki, Takahiro; Ide, Shunsuke; Urano, Hajime; Takechi, Manabu
no journal, ,
It is essential for a stable plasma equilibrium control to reconstruct an accurate plasma boundary in tokamak devices. Cauchy Condition Surface (CCS) method is a numerical approach to calculate the spatial distribution of the magnetic flux outside a hypothetical plasma surface and reconstruct the plasma boundary from the magnetic measurements located outside the plasma. It is found that the optimum number of unknown parameters and shape of the CCS for minimizing errors in the reconstructed plasma shape increase in proportion to the plasma size. It is shown that the accuracy of the plasma shape reconstruction greatly improves by using the optimum number of unknown parameters. The assessment of accuracy of plasma shape reconstruction by CCS method in JT-60SA is reported.
Nakamura, Shigetoshi; Shibama, Yusuke; Masaki, Kei; Sakasai, Akira
no journal, ,
no abstracts in English
Shimizu, Katsuhiro; Hoshino, Kazuo; Kawashima, Hisato; Takizuka, Tomonori*
no journal, ,
no abstracts in English
Tanigawa, Hisashi; Someya, Yoji; Nakamura, Makoto; Enoeda, Mikio
no journal, ,
Blanket is located on the vacuum vessel wall in the fusion reactor, and has functions of thermal energy transfer, tritium production and neutron shielding. In ITER, blanket does not have function of tritium production and coolant temperature is low because electric power generation is not planned. In the fusion reactor, the coolant temperature will be higher for the electric power generation and tritium breeding materials will be packed in the blanket. Therefore, safety-related characteristics of blanket are different for ITER and fusion reactor. In this study, thermal hydraulic behaviour in the blanket is analyzed to understand safety-related characteristic.
Yamanaka, Haruhiko; Watanabe, Kazuhiro; Kashiwagi, Mieko; Maejima, Tetsuya; Terunuma, Yuto; Umeda, Naotaka; Dairaku, Masayuki; Tobari, Hiroyuki; Hanada, Masaya
no journal, ,
no abstracts in English
Takeuchi, Masaki; Sugie, Tatsuo; Takeyama, Shigeharu; Itami, Kiyoshi
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no abstracts in English
Toma, Mitsunori; Hamamatsu, Kiyotaka; Hayashi, Nobuhiko; Honda, Mitsuru; Ide, Shunsuke
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no abstracts in English
Miyato, Naoaki; Yagi, Masatoshi; Scott, B. D.*
no journal, ,
Since the standard gyrokinetic model is constructed by the two-step phase space transformation, fluid moments can be represented in terms of a gyro-center distribution function and gyro-center coordinates in two ways. The representations of fluid moments are called push-forward representations. In the representation used in the standard gyrokinetic formulation, the gyro-center transformation part emerges as the pull-back transformation of the gyro-center distribution function and is separated from the guiding-center transformation part. In the alternative representation, the gyro-center part moves to the parts except the gyro-center distribution function and is combined with the guiding-center part. We compare the two representation by deriving explicit representations of particle flux.
Matsunaga, Go; Suzuki, Yasuhiro*; Shinohara, Koji; Ide, Shunsuke; Urano, Hajime
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no abstracts in English
Idomura, Yasuhiro
no journal, ,
Differences of confinement properties between hydrogen and deuterium plasmas are studied in numerical experiments of ion temperature gradient driven (ITG) turbulence using a full-f gyrokinetic code. Through systematic heating power and plasma size scans, it is found that a Bohm like scaling of the confinement time 
is given by stiff ion temperatur profiles, which are produced by intermittent bursts of avalanche like non-local transprt. Here, 
is the mass of ions and 
is the normalized Larmor radius. From this result, it is shown that the confinement time of the ion temperature gradient turbulence is proportional to the mass of ions.
Sugie, Tatsuo; Takeuchi, Masaki; Ishikawa, Masao; Shimada, Takahiko; Katsunuma, Atsushi*; Kitazawa, Daisuke*; Omori, Keisuke*; Itami, Kiyoshi
no journal, ,
no abstracts in English