Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Peterson, B. J.*; Seo, D. C.*; Konoshima, Shigeru; Kawashima, Hisato; Ashikawa, Naoko*; Parchamy, H.*; Liu, Y.*
no journal, ,
Resistive bolometers have problems with signal drift due to the uncompensated change in the background temperature of the detector. The electrical connections are susceptible to large changes in temperature. These characteristics render them ill suited for the application to steady-state fusion experiments. InfraRed imaging Video Bolometers (IRVB), on the other hand, are suited to steady state operation. The radiation is absorbed by the front surface of a thin foil and measured with an infrared camera. Temperature difference is taken with respect to the surrounding frame and no drift in the signal occurs. The materials are all metals and there are no electrical connections. IRVBs have been operated in LHD and JT-60U and are under design for KSTAR and planned for JT-60SA. Foil calibration and tomography techniques have been developed to provide poloidal profiles of the radiation emissivity.
Tamai, Hiroshi; JT-60SA Design Team
no journal, ,
In the JT-60SA project, schedule control for detailed design and construction is ioportant to keep 3 years of advantage prior to the start of ITER. The tokamak facilities are constructed by exchange of magnets, vacuum vessel, in-vessel components. Whereas the utilisation of existing JT-60 facilities is expected such as heating systems, diagnostics, power supplies. This is the constraint in the construction phase for the work in the main building. During the assembly work, some part of maintenance work of heating system, diagnostics will be still on going. The assembly schedule must be considered with the adjustment of newly conducted components and re-usage components. Procurement sharing with EU and Japan is important issue. Each part performs the detailed design, and manufacturing, testing, and shipping. The integrated schedule control is necessary to supervise the works at both sides. The plans for modification and the present status of the engineering design are presented.
Oikawa, Toshihiro; Polevoi, A. R.*; Mukhovatov, V.*; Shimada, Michiya; Bonoli, P.*; Campbell, D.*; Chuyanov, V.*
no journal, ,
In the ITER design review, reducing the NBI energy is proposed for increasing the plasma rotation. NBI capability is assessed for various design assumptions. In the D-T operation, reliable operation would be obtained well above the H-L transition boundary. In the hydrogen operation, the beam energy has to be less than 500keV due to the NBI shinethrough, and the H-mode operation regime is narrow. The NBI central heating at high density necessary for the ITER mission is difficult at 500keV. NB current drive decreases by 20% at 750keV, which makes it difficult to prospect the steady state scenario. The rotation increases by 13% at 750keV. Based on recent experiments, however, MHD instabilities can be suppressed at a rotation velocity available with 1MeV NBIs. A steady state scenario using LHCD is explored with a transport code employing a LHCD code. With a reasonable HH=1.4, 93% of the plasma current is no-inductively driven, and hence the pulse duration is extended to the machine limit.