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Journal Articles

Fabrication of 8Cr-2W ferritic steel tile for reduction in toroidal magnetic field ripple on JT-60U

Kudo, Yusuke; Sawai, Tomotsugu; Sakurai, Shinji; Masaki, Kei; Suzuki, Yutaka; Sasajima, Tadayuki; Hayashi, Takao; Takahashi, Ryukichi*; Honda, Masao; Jitsukawa, Shiro; et al.

Journal of the Korean Physical Society, 49(96), p.S297 - S301, 2006/12

Installation of ferritic steel tiles was proposed in JT-60U to reduce the toroidal magnetic field ripple and to improve the fast ion loss, which degrades heating efficiency and increases heat load on plasma facing component under large volume plasma operations. We selected a 8Cr-2W-0.2V ferritic steel with the cost-effectiveness, in which concentration limits of activation elements in F82H were relaxed because of the less number of neutron generations from deuterium operations on JT-60U. The fabricated ferritic steel has clear tempered martensitic microstructure, and sufficient magnetic and mechanical properties. The saturated magnetization was estimated to 1.7 Tesla at 573 K, lower than expected, but effectiveness in JT-60U was confirmed by numerical analyses. To research the effect of material conditions, such as microstructure and heat treatment, on saturated magnetization of the ferritic steel based on 8-9Cr is important for the future fusion reactors which will be planned to install the ferritic steel as the in-vessel components.

Journal Articles

Characterization of Type-I ELMs in tangential co-, balanced- and counter-plus perpendicular NBI heated plasmas on JT-60U

Kamiya, Kensaku; Urano, Hajime; Koide, Yoshihiko; Takizuka, Tomonori; Oyama, Naoyuki; Kamada, Yutaka; JT-60 Team

Plasma Physics and Controlled Fusion, 48(5A), p.A131 - A139, 2006/05

 Times Cited Count:21 Percentile:60.69(Physics, Fluids & Plasmas)

Effects of plasma rotation and ripple loss on the Type-I ELMs have systematically studied in the JT-60U tokamak, scanning combinations of NBI at the three kinds of plasma volumes. New findings on the Type-I ELMs confirm to be smaller ELM energy loss per pedestal stored energy, DWELM/Wped, and faster ELM frequency, fELM, in the counter-NBI than co-NBI, keeping the power of ELM, PELM, per heating power crossing the separatrix, PSEP, constant. Balanced-NBI case is also intermediate between co- and counter-NBI. In addition, the product of PELM/PSEP decreases according to increase in the plasma volume, suggesting an increase in the inter-ELM transport due mainly to an enhancement in the ripple loss of fast ion.

Journal Articles

The Roles of plasma rotation and toroidal field ripple on the H-mode pedestal structure in JT-60U

Urano, Hajime; Kamiya, Kensaku; Koide, Yoshihiko; Takizuka, Tomonori; Oyama, Naoyuki; Kamada, Yutaka; JT-60 Team

Plasma Physics and Controlled Fusion, 48(5A), p.A193 - A199, 2006/05

 Times Cited Count:10 Percentile:36.97(Physics, Fluids & Plasmas)

The characteristics of the H-mode pedestal structure were investigated by conducting the power scans for a variation of the toroidal momentum sources at different toroidal field ripple in JT-60U. It was found that the pedestal pressure is increased by reduced loss power of fast ions, independently of toroidal rotation. However, the energy confinement is improved with the CO-directed toroidal momentum source at H-mode plasmas with small ripple loss.

Journal Articles

Confinement of alpha particles in a low aspect ratio tokamak reactor

Tani, Keiji; Tobita, Kenji; Nishio, Satoshi; Iio, Shunji*; Tsutsui, Hiroaki*; Aoki, Takayuki*

Purazuma, Kaku Yugo Gakkai-Shi, 80(11), p.931 - 934, 2004/11

Studies were made on ripple losses of fusion produced alpha particles in a low-aspect-ratio tokamak reactor (VECTOR) by using an orbit-following Monte-Carlo code. Alpha particles are well confined in VECTOR. In a low-aspect-ratio tokamak, the dependence of ripple losses on the number of toroidal-field (TF) coils N is very weak. Assuming a toroidal peaking factor of 2 for the heat load due to loss particles, about 1.5% and 1.0% of TF ripple at the outer edge of plasma might be allowable for the first wall with and without cooling system, respectively. In both cases, the number of TF-coils can be reduced to about 4.

Journal Articles

Review of the history of experiments in the JFT-2M tokamak for 21 years

Miura, Yukitoshi; Hoshino, Katsumichi; Kusama, Yoshinori

Purazuma, Kaku Yugo Gakkai-Shi, 80(8), p.653 - 661, 2004/08

A series of experimental program on the JAERI Fusion Torus-2M (JFT-2M) was completed in March, 2004. In the experimental operation for 21 years since the first plasma on April 27, 1983, many significant results leading the fusion energy research and plasma physics have been produced in researches on high confinement mode (H-mode), heating and current drive, advanced plasma control, compatibility of low activation ferritic steel with improved confinement mode, etc. Among these results, some important results are presented.

JAEA Reports

Fast ion loss calculation in the ripple compensation magnetic field by ferritic steel insertion using the FEMAG/OFMC code

Urata, Kazuhiro*; Shinohara, Koji; Suzuki, Masanobu*; Kamata, Isao*

JAERI-Data/Code 2004-007, 45 Pages, 2004/03

JAERI-Data-Code-2004-007.pdf:5.63MB

As the toroidal magnetic field generated by discrete TF coils involves magnetic field ripple, the fast ion loss is induced to damage vacuum vessel in tokamaks. An idea of ripple compensation using ferromagnetic is proposed. Since low activation ferritic steel have low activation and thermal conduction properties, the ferritic steel is planned to install in tokamak reactors. Installation of ferritic steel plates with toroidal symmetry is effective to compensate ripple, however in the actual devices it is difficult for interference with other components. Besides the first wall shapes are often asymmetric. So it is better to treat toroidal asymmetry to evaluate the ripple induced loss in the actual devices. For the purpose, magnetic field calculation code considering ferritic steel; FEMAG(FErrite generating MAGnetic field)has been speeded up. On the basis of this magnetic field data, OFMC (Orbit Following Monte Carlo) has been upgraded to treat toroidal asymmetry. The use of FEMAG/OFMC, applications to the JFT-2M experiments, and the national centralized tokamak facility are reported.

Journal Articles

Tritium distribution in the first wall of JT-60U

Masaki, Kei; Sugiyama, Kazuyoshi*; Tanabe, Tetsuo*; Goto, Yoshitaka*; Tobita, Kenji; Miyo, Yasuhiko; Kaminaga, Atsushi; Kodama, Kozo; Arai, Takashi; Miya, Naoyuki

Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(2), p.130 - 139, 2003/06

no abstracts in English

JAEA Reports

Development of FEMAG; Calculation code of magnetic field generated by ferritic plates in the tokamak devices

Urata, Kazuhiro*

JAERI-Data/Code 2003-005, 36 Pages, 2003/03

JAERI-Data-Code-2003-005.pdf:2.96MB

In design of the fusion devises in which ferritic steel is planned to use as the plasma facing material and/or the inserts for ripple reduction, the appreciation of the error field effect and the optimization of ferritic plate arrangement to reduce the toroidal field ripple require calculation of ferritic magnetic field. However iterative calculations by the non-linearity in B-H curve disturbs high-speed calculation. In the strong toroidal magnetic field in the tokamak, fully magnetic saturation of ferritic steel occurs. Hence a distribution of magnetic charges as magnetic field source is determined straightforward. Additionally objective ferritic steel geometry is limited to the thin plate and they are installed along the toroidal magnetic field. Taking them into account, high-speed calculation code FEMAG has been developed. In this report, the formalization of FEMAG, how to use FEMAG, and the validity check in comparison with a 3D FEM code, with the measurements of the magnetic field in JFT-2M are described. The presented examples are design studies for JT-60 modification.

Journal Articles

Tritium distribution in JT-60U W-shaped divertor

Masaki, Kei; Sugiyama, Kazuyoshi*; Tanabe, Tetsuo*; Goto, Yoshitaka*; Miyasaka, Kazutaka*; Tobita, Kenji; Miyo, Yasuhiko; Kaminaga, Atsushi; Kodama, Kozo; Arai, Takashi; et al.

Journal of Nuclear Materials, 313-316, p.514 - 518, 2003/03

 Times Cited Count:52 Percentile:95.22(Materials Science, Multidisciplinary)

Detailed tritium profiles on the JT-60U W-shaped divertor and first wall tiles were examined by Tritium Imaging Plate Technique (TIPT) and full combustion method. The tritium deposition image obtained by TIPT was consistent with the distribution measured by combustion method. The highest tritium concentration was 60 kBq/cm$$^{2}$$ at the dome top tile. However, deposition layer was not obviously observed on the dome top tile. The tritium concentration in the inner divertor target tile was lower (2 kBq/cm$$^{2}$$) even with the thick deposition layer of $$sim$$60 $$mu$$m. This tritium distribution can be explained by energetic triton particle loss due to ripple loss. According to the simulation using the OFMC code, 31% of the triton particles produced by D-D nuclear reaction is implanted deeply to the wall without fully losing the initial energy of 1 MeV.

Journal Articles

Energetic particle experiments in JT-60U and their implications for a fusion reactor

Tobita, Kenji; Kusama, Yoshinori; Shinohara, Koji; Nishitani, Takeo; Kimura, Haruyuki; Kramer, G. J.*; Nemoto, Masahiro*; Kondoh, Takashi; Oikawa, Toshihiro; Morioka, Atsuhiko; et al.

Fusion Science and Technology (JT-60 Special Issue), 42(2-3), p.315 - 326, 2002/09

 Times Cited Count:8 Percentile:50.12(Nuclear Science & Technology)

Energetic particle experiments in JT-60U are summarized, mainly covering ripple loss and Alfven eigenmodes (AE modes). Significant loss was observed for 85 keV NBI ions and fusion-produced tritons increased when toroidal field ripple at the plasma surface, especially in reversed shear plasma. Measurement of hot spots on the first wall due to ripple loss confirmed agreement with code predictions, validating the modeling incorporated in an orbit-following Monte Carlo code. A variety of AE modes were destabilized in ICRF minority heating and negative-ion-based NBI (N-NBI) heating. Most of the observed modes are gap modes identified to be TAE, EAE and NAE. Interesting finding is pulsating modes accompanying frequency sweep, which were destabilized by N-NBI and sometimes induced a beam ion loss of up to 25%. Also presented are energetic particle issues in auxiliary heating with ICRF and N-NBI.

Journal Articles

Energetic particles in spherical torus

Tobita, Kenji

Denki Gakkai Kenkyukai Shiryo, Pulazuma Kenkyukai (PST-01-73), p.43 - 46, 2001/09

Behavior of energetic particles in spherical torus (ST) is summarized in comparison with that in tokamaks. The issues treated in this article are neoclassical transport, ripple loss, Alfven eigenmodes and Magetohydrodynamic- instability-induced anomalous transport. ST is expected to be favorable in terms of neoclassical transport and ripple loss. On the other hand, Alfven eigenmodes and the resulting energetic particle loss can be serious concerns in a ST reactor because of a high volume-averaged beta and a super-Alfvenic speed of alpha particles.

Journal Articles

Unsteady motion of parastic-capillary ripples on the gravity waves

Seki, Kosuke*; Tsuji, Yoshiyuki*; Kondo, Masaya; Kukita, Yutaka*

Nihon Kikai Gakkai 2001-Nendo Nenji Taikai Koen Rombunshu, p.9 - 10, 2001/00

no abstracts in English

Journal Articles

Triton burnup measurements using scintillating fiber detectors on JT-60U

Nishitani, Takeo; Isobe, Mitsutaka*; G.A.Wurden*; R.E.Chrien*; Tobita, Kenji; Kusama, Yoshinori; Harano, Hideki*

Fusion Engineering and Design, 34-35, p.563 - 566, 1997/00

 Times Cited Count:15 Percentile:75.71(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Triton burn-up study in JT-60U

Nishitani, Takeo; Hoek, M.; Harano, Hideki*; Isobe, Mitsutaka*; Tobita, Kenji; Kusama, Yoshinori; Wurden, G. A.*; Chrien, R. E.*

Plasma Physics and Controlled Fusion, 38(3), p.355 - 364, 1996/03

 Times Cited Count:31 Percentile:71.16(Physics, Fluids & Plasmas)

no abstracts in English

JAEA Reports

Effect of ion $$nabla$$B drift direction on ripple-induced fast ion loss in JT-60U

Isobe, Mitsutaka*; Tobita, Kenji; Nishitani, Takeo; Kusama, Yoshinori; *

JAERI-Research 96-005, 11 Pages, 1996/02

JAERI-Research-96-005.pdf:0.46MB

no abstracts in English

Journal Articles

Triton burnup study in JT-60U

Nishitani, Takeo; M.Hoek*; Harano, Hideki*; G.A.Wurden*; R.E.Chrien*; Isobe, Mitsutaka*; Tobita, Kenji; Kusama, Yoshinori

22nd European Physical Society Conf. on Controlled Fusion and Plasma Physics,Vol. 19C,Part II, 0, p.2.061 - 2.064, 1995/00

no abstracts in English

Journal Articles

Plasma simulator METIS for tokamak confinement and heating studies

; Tani, Keiji; Tsunematsu, Toshihide; Kishimoto, Yasuaki; ; *; *

Parallel Computing, 18, p.743 - 765, 1992/00

 Times Cited Count:2 Percentile:53.82(Computer Science, Theory & Methods)

no abstracts in English

Journal Articles

Rippled pattern of image in HVEM irradiated nickel

; ; ;

Japanese Journal of Applied Physics, 25(12), p.L964 - L966, 1986/12

 Times Cited Count:0 Percentile:0.01(Physics, Applied)

no abstracts in English

JAEA Reports

Magnetic Structure of Poloidal Divertor Configuration with Non-Axisymmetric Perturbed Field in JT-60

Yoshida, H.; ; ; Sengoku, Seio; ; ; ;

JAERI-M 9789, 28 Pages, 1981/11

JAERI-M-9789.pdf:0.64MB

no abstracts in English

JAEA Reports

Behavior of Radial Electric Field and Inpurity Transport in Tokamak

JAERI-M 8750, 92 Pages, 1980/03

JAERI-M-8750.pdf:2.09MB

no abstracts in English

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