Status of development of Lithium Target Facility in IFMIF/EVEDA project

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 250C 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.

Safety-related behaviour of water-cooled solid breeder blanket

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.

Toroidal plasma flow and radial electric field structures at the separatrix in JT-60U ELMy H-mode plasmas

Kamiya, Kensaku; Honda, Mitsuru; Urano, Hajime; Yoshida, Maiko; Kamada, Yutaka

no journal, , 

In this study, we perform to identify the boundary condition for the toroidal plasma flow, which is known to play an important role for an improved plasma stability and/or confinement, to improve the prediction in the plasma core region by a code, experimentally. Boundary condition of toroidal plasma flow imposed at the separatrix in JT-60U ELMy H-mode plasmas has been identified, comparing between co- and counter-NBI discharges. Toroidal plasma flow at the separatrix can become non-zero value, varying with momentum input direction, but being unaffected by the ELM event. The results indicate that the viscosity damping due to SOL flow through ion-neutral collision may not affect strongly ion parallel momentum transfer.

Analysis of JT-60U experiments by extended kinetic-MHD model

Shiraishi, Junya; Miyato, Naoaki; Matsunaga, Go

no journal, , 

no abstracts in English

Toroidal rotation modeling with the 3D non-local drift-kinetic code and boundary models for JT-60U analyses and predictive simulations

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

Optimization of the magnetic configlation toward large current beam production in the JT-60SA negative ion source

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.

Design of top lid structure in JT-60SA cryostat

Nakamura, Shigetoshi; Shibama, Yusuke; Masaki, Kei; Sakasai, Akira

no journal, , 

no abstracts in English

Developments of a JT-60SA Thomson scattering diagnostic

Tojo, Hiroshi; Hatae, Takaki; Sakuma, Takeshi; Hamano, Takashi; Itami, Kiyoshi; Suito, Satoshi*; Araki, Takashi*; Iwamoto, Kohei*; Takeda, Yuya*

no journal, , 

Multi-scale simulations of electron- and ion-scale turbulence in magnetic fusion plasma

Maeyama, Shinya

no journal, , 

Gyrokinetic simulation of electron turbulence spectrum

Kawai, Chika; Maeyama, Shinya; Idomura, Yasuhiro; Ogawa, Yuichi*

no journal, , 

Self-organization through inverse cascades of energy in a turbulent spectrum is considered as one of the paths to formation of zonal flow structures in magnetized plasma. Despite the theoretical suggestion, relations between the turbulence energy spectrum and the formation of zonal flow structures have not been rigorously investigated in terms of numerical simulation studies based on a first-principle model. In this study, spectrum structures of electron scale plasma turbulence are obtained from high-resolution Vlasov simulations. The long wave length region of the spectrum is investigated in relation with self-organization.