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Kobayashi, Tatsuya*; Ito, Kimitaka*; Ido, Takeshi*; Kamiya, Kensaku; Ito, Sanae*; Miura, Yukitoshi; Nagashima, Yoshihiko*; Fujisawa, Akihide*; Inagaki, Shigeru*; Ida, Katsumi*; et al.
Scientific Reports (Internet), 6, p.30720_1 - 30720_7, 2016/08
Times Cited Count：13 Percentile：64.47(Multidisciplinary Sciences)In this Letter, we report model verifications for a key physics for the L-H transition. Radial electric field excitation, using discharges having a two-step transition. Examining time derivative of Poissons equation, it is found that the sum of the loss cone loss current and neoclassical bulk viscosity current agrees the experimentally observed current in the order of magnitude at the first transition. Following second transition and an ambipolar condition in the L-mode cannot be explained by the models.
Kamiya, Kensaku; Honda, Mitsuru; Urano, Hajime; Yoshida, Maiko; Kamada, Yutaka; Ito, Kimitaka*; JT-60 Team
Physics of Plasmas, 21(12), p.122517_1 - 122517_8, 2014/12
Times Cited Count：13 Percentile：54.18(Physics, Fluids & Plasmas)Modulation Charge eXchange Recombination Spectroscopy (MCXRS) measurements with high spatial and temporal resolution have made the evaluation of the toroidal plasma flow of fully stripped carbon impurity ions in the JT-60U tokamak peripheral region (including in particular separatrix) possible with a better signal-to-noise ratio. Boundary condition of Vt imposed at the separatrix in ELMy H-mode plasmas has been identified, comparing between co- and counter-NBI discharges. The Vt value at the separatrix is not held fixed at the zero, varying with momentum input direction, but being not strongly affected by the ELM event. A non-zero Vt value at the separatrix might be connected to fast ion losses due to toroidal field ripple that results in formation of a negative radial electric field (Er) layer having almost zero (or very weak positive) Er-shear value at the separatrix. Improved understanding of physics process in pedestal structure formation for the Vt and Er is also discussed.
-mode plasmas in JT-60U tokamakUrano, Hajime; Takizuka, Tomonori; Takenaga, Hidenobu; Oyama, Naoyuki; Miura, Yukitoshi; Kamada, Yutaka
Nuclear Fusion, 46(8), p.781 - 787, 2006/08
Times Cited Count：22 Percentile：58.85(Physics, Fluids & Plasmas)The degradation of energy confinement with increased toroidal beta 
was shown by the non-dimensional analysis in JT-60U. The dependence of the energy confinement on was examined by both the JT-60U ELMy 
-mode confinement database and the dedicated experiment on a single scan while 
and 
were kept fixed as well as the other magnetic geometrical parameters. In both cases, the degradation of energy confinement with increasing was observed, satisfying the relation of 
. This dependence is a little weaker than that predicted by the IPB98(y,2) scaling. The fusion power production rate was estimated to increase in proportion to 
.
Takizuka, Tomonori; Urano, Hajime; Takenaga, Hidenobu; Oyama, Naoyuki
Plasma Physics and Controlled Fusion, 48(6), p.799 - 806, 2006/06
Times Cited Count：16 Percentile：48.35(Physics, Fluids & Plasmas)Dependence of the ELMy H-mode confinement on the beta has been investigated for a long time, but a common conclusion has not yet been obtained.The IPB98(y,2) scaling shows a strong degradation with beta, while DIII-D and JET experiments exhibited the absence of the beta degradation. Recent JT-60U experiment demonstrated that the strong beta degradation really exists for the ELMy H-mode. In the present paper, we analyze the JT-60U ELMy H-mode confinement database and confirm the strong power degradation of the confinement time, which corresponds to the strong beta degradation consistent with the above result. We analyze also the ITPA H-mode confinement database in detail. How the beta dependence of the confinement time is changed by the externally given parameters, such as the shape parameters, are investigated.
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：34.26(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.
Kamiya, Kensaku; Oyama, Naoyuki; Ido, Takeshi*; Bakhtiari, M.*; JFT-2M Group
Physics of Plasmas, 13(3), p.032507_1 - 032507_9, 2006/03
Times Cited Count：14 Percentile：43.86(Physics, Fluids & Plasmas)Accompanying the HRS H-mode transition, the coherent magnetic fluctuations in the frequency range of the order of 10-100 kHz with significant variation are seen on the magnetic probes at the vessel wall. Above all, two types of edge MHD activities, which have associated toroidal mode number of n=1 and n
7, respectively, seem to be more important for the HRS H-mode plasmas. To investigate their interaction, bi-spectral analysis is applied for the magnetic probe data. It is found to be a powerful tool, exhibiting the phase-coupled oscillations between two types of edge MHD activities having n=1 and n7.
Kamiya, Kensaku; Kawashima, Hisato; Ido, Takeshi*; Oyama, Naoyuki; Bakhtiari, M.*; Kasai, Satoshi; Kusama, Yoshinori; Miura, Yukitoshi; Ogawa, Hiroaki; Tsuzuki, Kazuhiro; et al.
Nuclear Fusion, 46(2), p.272 - 276, 2006/02
Times Cited Count：3 Percentile：10.78(Physics, Fluids & Plasmas)An attractive operational regime without any large ELMs, namely High Recycling Steady (HRS) H-mode, was found on JFT-2M during Y2000 campaign after boronization. Recent experiments have concentrated on the studies of the access conditions for the HRS regime, in terms of the pedestal parameters. The HRS regime was more likely at higher edge density and lower edge temperature, which corresponds to the normalized electron collisionality of 1 in the plasma edge region.
and collisionality approaching ITER conditionsCordey, J. G.*; Thomsen, K.*; Chudnovskiy, A.*; Kardaun, O. J. W. F.*; Takizuka, Tomonori; Snipes, J. A.*; Greenwald, M.*; Sugiyama, L.*; Ryter, F.*; Kus, A.*; et al.
Nuclear Fusion, 45(9), p.1078 - 1084, 2005/09
Times Cited Count：51 Percentile：82.4(Physics, Fluids & Plasmas)The condition of the latest version of the ELMy H-mode database has been re-examined. It is shown that there is bias in the ordinary least squares regression for some of the variables. To address these shortcomings three different techniques are employed: (a)principal component regression, (b)an error in variables technique and (c)the selection of a better conditioned dataset with fewer variables. Scalings in terms of the dimensionless physics valiables, as well as the standard set of engineering variables, are derived. The new scalings give a very similar performance for existing scalings for ITER at the standard beta, but a much improvement performance at higher beta.
Oyama, Naoyuki; Sakamoto, Yoshiteru; Isayama, Akihiko; Takechi, Manabu; Gohil, P.*; Lao, L. L.*; Snyder, P. B.*; Fujita, Takaaki; Ide, Shunsuke; Kamada, Yutaka; et al.
Nuclear Fusion, 45(8), p.871 - 881, 2005/08
Times Cited Count：119 Percentile：95.42(Physics, Fluids & Plasmas)The grassy ELM is characterized by the high frequency periodic collapse up to kHz, which is 15 times faster than that for type I ELM. A divertor peak heat flux due to grassy ELMs is less than 10% of that for type I ELMs. This smaller heat flux is caused by narrower radial extent of the collapse of temperature pedestal. The different radial extent between type I ELMs and grassy ELMs qualitatively agrees with the different radial distribution of the eigen function of the ideal MHD stability analysis. The ratio of ELM energy loss for grassy ELMs to the pedestal stored energy was 0.4-1%. In high triangularity regime, ELM amplitude, frequency and type can be changed from type I ELM to high frequency grassy ELM as counter plasma rotation was increased. In low triangularity regime, on the other hand, the complete ELM suppression (QH-mode) has been achieved, when the plasma position is optimized with CTR-NBIs. The existence of the edge fluctuations localized in pedestal region may reduce the pedestal pressure, and therefore the QH-mode can be sustained for long time up to 3.4s.
Kamiya, Kensaku; Oyama, Naoyuki; Miura, Yukitoshi; Hubbard, A. E.*
Plasma Physics and Controlled Fusion, 46(11), p.1745 - 1755, 2004/11
Times Cited Count：13 Percentile：40.22(Physics, Fluids & Plasmas)Recent experiments in the JFT-2M tokamak have concentrated on the studies of the access condition for the H-mode operation without any large ELMs, namely High Recycling Steady (HRS) H-mode regime in terms of the pedestal parameters. The HRS regime is more likely at the higher edge density and lower edge temperature, while the ELMy H-mode having large ELMs appears at the lower edge density and higher edge temperature. It is found that the ELMy/HRS operational boundary occurs at the normalized electron collisionality of 
*
1 in the plasma edge region, depending slightly on q
. A key feature of the HRS H-mode is the presence of the coherent magnetic fluctuations in the frequency range of the order of 10-100 kHz. It is suggested that the edge MHD activities may keep an edge pressure below a certain level needed to induce a large ELM.
Kawashima, Hisato; Uehara, Kazuya; Nishino, Nobuhiro*; Kamiya, Kensaku; Tsuzuki, Kazuhiro; Bakhtiari, M.; Nagashima, Yoshihiko*; Ogawa, Hiroaki; Hoshino, Katsumichi; Suzuki, Sadaaki; et al.
Purazuma, Kaku Yugo Gakkai-Shi, 80(11), p.907 - 908, 2004/11
A comparison of divertor heat load between ELMy and "High Recycling Steady" (HRS) H-mode was carried out by fast measurements of the two dimensional 
emission, and the divertor electron temperature and ion saturation current on JFT-2M. They brought an attractive feature of HRS H-mode that the heat load was reduced to the level on time average that for ELMy H-mode, being able to avoid the severe heat load during pulsed ELM event. It was also indicated that the HRS H-mode was dominated by an enhancement of particle transport, whereas both heat and particle transport increased abruptly at ELM event.
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.
Kamiya, Kensaku; Bakhtiari, M.; Kasai, Satoshi; Kawashima, Hisato; Kusama, Yoshinori; Miura, Yukitoshi; Ogawa, Hiroaki; Oyama, Naoyuki; Sato, Masayasu; Shinohara, Koji; et al.
Plasma Physics and Controlled Fusion, 46(5A), p.A157 - A163, 2004/05
Times Cited Count：21 Percentile：56.48(Physics, Fluids & Plasmas)A new operating regime, High Recycling Steady (HRS) H-mode regime, has been discovered on JFT-2M, which is easily reproduced under the wall fueling from the boronized first wall. Accompanying the HRS H-mode transition, the coherent magnetic and floating potential fluctuations are seen on magnetic probes at vessel wall and Langmuir probe in SOL, respectively. These coherent fluctuations have a frequency of the order of 10-100 kHz with significant variation, which is recognized to be important to enhance the particle transport. The HRS can be seen even at 
3 with 
/
0.4 for the fixed delta0.4 in the standard single-null divertor configuration. Recent experimental results from JFT-2M show that the plasma shape also seems to play an important role in determining the type of ELMs. The HRS regime can be extended up to delta0.75 and 2.6 in the double-null configuration, while lower delta boundary exists at delta0.3 with moderate 4 even at high recycling and/or density condition of /0.4.
and effective 
of the H-mode power threshold in tokamaks of the ITPA databaseTakizuka, Tomonori; ITPA H-mode Threshold Database Working Group*
Plasma Physics and Controlled Fusion, 46(5A), p.A227 - A233, 2004/05
Times Cited Count：56 Percentile：84.55(Physics, Fluids & Plasmas)To evaluate the H-mode power threshold in future tokamak reactors, quantitative scaling formulas have been developed by using the ITPA threshold database. Recently data from spherical tokamaks (MAST and NSTX) were supplied to the ITPA database. A new scaling expression, which includes the absolute magnetic field B instead of the toroidal magnetic field, subsumes the plasma current dependence at low aspect ratio and is consistent with the previous data without any explicit current dependence. Other possible influence of the low aspect ratio to increase the power threshold is also investigated. It is cralified for the whole data set that the effective charge number Z raises the power threshold. By adding Z as a parameter of the scaling expression, both the scattering nature and the low-density anomaly found in the experimental data can be reduced.
Sakamoto, Yoshiteru; Shirai, Hiroshi; Fujita, Takaaki; Ide, Shunsuke; Takizuka, Tomonori; Oyama, Naoyuki; Kamada, Yutaka
Plasma Physics and Controlled Fusion, 46(5A), p.A299 - A304, 2004/05
Times Cited Count：68 Percentile：88.54(Physics, Fluids & Plasmas)no abstracts in English
Fujita, Takaaki; JT-60 Team
Nuclear Fusion, 43(12), p.1527 - 1539, 2003/12
Times Cited Count：32 Percentile：68.11(Physics, Fluids & Plasmas)Recent JT-60U results toward high integrated performance are reported with emphasis on the projection to the reactor-relevant regime. N-NB and EC power increased up to 6.2 MW and 3 MW, respectively. A high betap H-mode plasma with full non-inductive current drive has been obtained at 1.8 MA and the fusion triple product reached 3.1E20m
keVs. NTM suppression with EC was accomplished using a real-time feedback control system and improvement in betaN was obtained. A stable existence of current hole was observed. High DT-equivalent fusion gain of 0.8 was maintained for 0.55 s in a plasma with a current hole. The current profile control in high bootstrap current reversed shear plasmas was demonstrated using N-NB and LH. A new operation scenario has been established in which a plasma with high bootstrap current fraction and ITBs is produced without the use of OH coil. A new type of AE mode has been proposed and found to explain the observed frequency chirp quite well. Ar exhaust with EC heating was obtained in a high betap mode plasma.
Kamiya, Kensaku; Kimura, Haruyuki; Ogawa, Hiroaki; Kawashima, Hisato; Tsuzuki, Kazuhiro; Sato, Masayasu; Miura, Yukitoshi; JFT-2M Group
Nuclear Fusion, 43(10), p.1214 - 1219, 2003/10
no abstracts in English
Kamiya, Kensaku; Kimura, Haruyuki; Ogawa, Hiroaki; Kawashima, Hisato; Tsuzuki, Kazuhiro; Sato, Masayasu; Miura, Yukitoshi; JFT-2M Group
Nuclear Fusion, 43(10), p.1214 - 1219, 2003/10
Times Cited Count：35 Percentile：70.78(Physics, Fluids & Plasmas)no abstracts in English
Sugihara, Masayoshi; Mukhovatov, V.*; Polevoi, A.*; Shimada, Michiya
Plasma Physics and Controlled Fusion, 45(9), p.L55 - L62, 2003/09
Times Cited Count：40 Percentile：74.98(Physics, Fluids & Plasmas)Improvement of the scaling of H-mode edge pedestal pressure for a Type-I ELM regime based on a simple analytical formula is achieved by introducing shaping factors into the scaling. The physics basis of these shaping factors is an enhancement of the critical pressure gradient by the magnetic well. With increasing the magnetic well, a high toroidal mode number ideal ballooning mode and peeling mode decouple and critical gradient is determined by intermediate mode number, which results in significant enhancement of the critical pressure gradient. The improved scaling can reproduce the pedestal pressure reasonably well for ASDEX-U, JET, DIII-D and JT-60U Type-I ELmy data archived in the ITER pedestal database.
JT-60 Team
JAERI-Review 2002-022, 149 Pages, 2002/11
JAERI-Review-2002-022.pdf:10.21MB
no abstracts in English
