Study of Current Decay Time during Disruption in JT-60U Tokamak

Size: px
Start display at page:

Download "Study of Current Decay Time during Disruption in JT-60U Tokamak"

Transcription

1 1 EX/7-Rc Study of Current Decay Time during Disrution in JT-60U Tokamak M.Okamoto 1), K.Y.Watanabe ), Y.Shibata 3), N.Ohno 3), T.Nakano 4), Y.Kawano 4), A.Isayama 4), N.Oyama 4), G.Matsunaga 4), K.Kurihara 4), M.Goto ), S.Sakakibara ), M.Sugihara 5) and Y.Kamada 4) and JT-60 team 4) 1) Ishikawa National College of Technology, Ishikawa , Jaan ) National Institute for Fusion Science, Toki , Jaan 3) Graduate School of Engineering, Nagoya University, Nagoya , Jaan 4) Jaan Atomic Energy Agency, Ibaraki , Jaan 5) ITER Organization, Cadarache, France contact of main author: okamoto@ishikawa-nct.ac.j Abstract. The lasma current decay time during initial hase of the radiation induced disrution in JT-60U tokamak is studied based on the lasma inductance and resistance estimated by exerimental data. The features of this study are as follows; (i) the electron temerature rofile during the current quench is estimated by the electron cyclotron emission (ECE) diagnostic systems and the measurement of He I line emission intensity ratios, and the lasma inductance is estimated by the CCS (Cauchy-Condition Surface) method with the magnetics [1]. (ii) in the radiation induced disrution lasmas, it is found that the time change rate of the lasma inductance during current quench is an imortant arameter as well as the lasma resistance to redict the current decay time. 1. Introduction Disrution is one of the most crucial issues for the tokamak fusion reactors. Intense eddy currents and large halo currents generated during the current quench of the disrution induce large electromagnetic forces on the vacuum vessel and in-vessel comonents. The forces could be large enough to mechanically break the in-vessel comonents []. In order to estimate the force induced by eddy currents, recise rediction of lasma current decay time is imortant. The database for ITER (International Thermonuclear Exerimental Reactor) [3] is established by using the current decay time τ normalized by the lasma cross-sectional area S. The area-normalized τ is induced by the L/R model based on a simle series circuit of the lasma resistance R and inductance L, where τ can be described by L /R. In this model, τ/s can be reresented by (L /πr 0 )/η, it is little deendence on the device size and is strongly deendence on the electron temerature T e and effective charge Z eff, where R 0 and η are the lasma major radius and resistivity, resectively. In the database, the lower bound on areanormalized τ, which is taken as 1.7 ms/m [4], is used as the criterion value for design of ITER. In order to exerimentally evaluate the validity of the L/R model, very low T e and Z eff during current quench must be measured by the diagnostic system with high time resolution. D. G. Whyte and D.A.Humhrevs had estimated the T e and Z eff during current quench using measurement of helium recombination radiation and reorted the relation between the current decay time and classical resistivity [5,6]. However, the systematic analysis of the current decay time and electron temerature during current quench has not reorted yet. In this aer, the T e rofile during current quench is estimated by ECE diagnostic systems and measurement of He I emission intensity ratios. We verify the validity of L/R model using the initial hase of current quench of radiation induced disrutive lasma with τ/s = 5 ~ 40 ms/m. The measurement of T e using ECE diagnostic systems in lasma core region is

2 EX/7-Rc ossible during initial hase of slow current decay disrution in JT-60U Tokamak. In the edge region, T e can be estimated by He I emission intensity ratio. The fundamental validity of the T e measurement based on He I emission line intensity ratio was confirmed by comaring with T e measurement by Langmuir robes in JT-60U [7] and NAGDIS-II [8], etc. According to ref. 7, T e estimated by He I line intensity ratio is almost same with T e by the robe within the factor of and the former is systematically smaller than the latter. We analyze 9 disrutive lasma shots with massive neon gas uffing. The safety factor, toroidal magnetic strength and NBI ower just before current quench is not same among the shots. In addition, the time evolution of lasma inductance during current quench is focused, and relation between current decay time and lasma inductance is evaluated. The equilibrium calculation of MHD, which is calculated by the CCS method, is used to estimate the lasma inductance.. Model of Current Decay Time If tokamak lasma is assumed to be reresented by a simle series circuit consisting of R and L, the energy conservation equation is exressed as 1 t t 1 L I + R 0 I dt = V 0 exi dt + L 0I 0, (1) where I and V ex is the lasma current and the externally alied voltage, L 0 and I 0 is lasma inductance and current just before current quench, resectively. When Eq. 1 is transformed, it becomes the following circuit equation: 1 L & I + LI& + R I = Vex. () In the small tokamaks, the right-hand side of Eq. cannot be neglect because the absolute value of the left-hand side of Eq. is the same order of magnitude as the absolute value of V ex [9]. On the other hand, the absolute value of V ex is usually smaller than the left-hand side of Eq. in the large tokamaks. This characteristic becomes more remarkable when device size becomes large. If R and L are constant in time, and V ex can be neglect, the temoral evolution of I can be exressed by the following equation, I = I 0 ex( t / τ L / R ), (3) where τ L/R = L /R is the time constant of I decay. Equation 3 is valid when the current decay time is very short and lasma resistance is sufficiently large. When the current decay time can be aroximated by τ L/R = L /R, the area-normalized current decay time τ /S can be exressed as τ L L R / πr / 0 =, (4) S η where R 0 is the lasma major radius, η is the lasma resistivity, and η = R S/πR 0. τ L/R /S has little deendence on the device size, because L is aroximately roortional to R 0, and has a strong deendence on η, which is rimarily determined by T e and Z eff in the classical Sitzer formula [10]. Thus, the database for ITER rediction is established in terms of the area-normalized current decay time τ /S [3]. However, when R and L greatly change in time, Eq. 4 cannot be valid. Therefore, to verify the L/R model, it is necessary to measure L and R in time during current quench exerimentally. 3. Exerimental Result 3.1. Relation Between Area-normalized Current Decay Time and Plasma Resistivity

3 3 EX/7-Rc In this aer, we study the current decay time in the radiation induced disrution by the massive neon gas uffing. The tyical waveform of lasma current I, line integrated electron density n e, lasma stored energy W and gas ressure of neon at disrution are shown in Fig. 1. After neon gas uffing, line integrated n e is gradually increased and W is decreased, and then the current quench and raid increase of line integrated n e are observed. We focus on the current decay during the initial hase of the current quench shown by the region enclosed by dotted line in Fig. (a), where I dros by 10%, because the T e rofile can be estimated by ECE diagnostic systems exerimentally. The exerimental current decay time during initial hase of current quench is defined by the following equation, τ % = I 0 ( I / t), (5) where I 0 is the lasma current at the current quench start time. In this discharge, thermal quench is haened around at sec and current quench is started about at 1.09 sec. From Fig. (c), it is found that T e rofile becomes flat at thermal quench and then returns to a eaked rofile in the initial hase. In this hase, T e in the core region is about 400 ev. Roughly seaking, because the otical thickness is small at T e < 100 ev, the sensitivity of ECE diagnostic systems becomes low and T e at normalized minor radius ρ > 0.4 cannot be estimated by ECE diagnostic systems. Here we use the He I emission intensity ratio method in (a) (b) t I FIG. 1. The tyical waveform of radiation induced disrution in JT-60U. (c) (d) (e) FIG. 3. Poloidal cross-section view of JT-60U lasma. Blue line means the line of sight for HeI sectroscoy. FIG.. The evaluation of (a) lasma current I and (b) electron temerature T e measured by ECE diagnostic system, (c) major radial rofile of T e., (d) He I emission intensity and (e) electron temerature by using HeI emission Intensity ratios method.

4 4 EX/7-Rc the case that the estimated T e by ECE is less than 100 ev. In order to measure the electron temerature, it is necessary to to measure three He I lines at the same time of ( 1 P 3 1 D), ( 3 P 3 3 S) and 78.1 nm ( 1 P 3 1 S) resectively. A sectrometer equied with three band ass interference filters makes it ossible to measure the time evolution of T e with a sufficient time resolution. Figure 3 shows the line of sight for measurement of ECE (crosses) and He I emission intensity (solid line). The He I emission intensity is measured from the outer diverter region though the edge region of ρ > 0.7. Figure (d) and (e) shows the measurement result of He I emission intensity and the estimated electron temerature. From Fig. (d), it is found that He I emission intensity increase raidly about at t = sec, which is the thermal quench start time. Before the thermal quench, the He I emission mainly comes from the diverter region because He neutrals only exist in this region. On the other hand, after the thermal quench, the He I emission comes from the edge region also because T e raidly decreases in the whole region due to the thermal quench. Since the measurement value of He I emission intensity is the integration value on line of sight and the measurement osition of T e estimated by He I emission intensity ratio cannot secify, it s osition is assumed ρ = 0.7. FIG. 4. Profile of electron temerature measured by ECE systems and He I sectroscoy at t = sec. Figure 4 shows the assumed T e rofile using measurement values of ECE diagnostic systems and He I emission intensity ratios method at t = sec. In this figure, oened circles and cross mean T e estimated by ECE systems and He I sectroscoy, resectively. The T e of ρ = and is assumed by a linear function. Unfortunately, we cannot obtain the accurate rofile of the lasma resistivity because the lasma effective charge Z eff cannot be measured in the initial hase of current quench. In order to seculate Z eff, we use the ionic fraction data of neon calculated by Arnaud and Rohtenflug [11]. If the mixing ratios of deuterium and neon gas are 9 : 1, 7 : 3 and 1 : 1 and these ratios are uniform in sace, the calculation results of Z eff and η are shown in Fig. 5. The η is calculated by Sitzer formula and assumed Z eff. In Fig. 5, the uer and lower values of error bar are values calculated using assumtions of D : Ne = 1 : 1 and 9 : 1, resectively. The values of Z eff in the core and edge region are about 7 and, resectively. In order to investigate the relation between area-normalized τ and lasma resistivity, we FIG. 5. Profile of lasma effective charge and resistivity at t = sec. The effective charge is calculated using the assumtion of D : Ne = 9 : 1, 7 : 3 and 1 : 1. FIG. 6. The area-normalized current decay time as a function the area-averaged T e -3/

5 5 EX/7-Rc use area-averaged T e -3/ calculated by T 3/ = ( / 3/ e S S T e ), (6) where S is the lasma cross-section area. This value is roortional to the area-averaged lasma resisitivity η with Z eff = 1. The area-averaged η can be estimated by η rofile in Fig.5 and following equation, η = S ( S / η ). (7) The relation between area-normalized τ and area-averaged T -3/ e is shown in Fig. 6. In Fig. 6, the T is calculated by Eq. 6 and the rofile of time averaged T -3/ e during the initial 3/ e hase of current quench. In the similar way, τ L/R /S is calculated by Eq. 4, 7 and the rofile of time averaged η. The uer and lower values of error bar of τ L/R /S are values calculated using assumtions of D : Ne = 9 : 1 and 1 : 1, resectively. It is found that the exerimental areanormalized τ is indeendent of the area-averaged T e -3/ and the rediction area-normalized decay time τ L/R /S calculated from L/R model is much longer than the exerimental value, esecially in the case of small exerimental values. It seems that this result means the L/R model does not verify and L is not constant and greatly changes in time during initial hase of current quench. 3.. Time Evolution of Plasma Inductance using CCS Method We use the CCS method using magnetic sensor signals due to evaluate the temoral evolution of lasma inductance and lasma shae. This method can obtain the exact analytical solution based on the boundary element method using a static Maxwell equation with a Green function in a toroidal axisymmetric region [1]. In a case of several magnetic sensors, we can obtain the aroximate solution of the magnetic field and flux according to the accuracy and the number of sensors. It was confirmed that the error of Shafranov lambda value calculated by this method is less than 0.1 in JT-60U measurement systems, which have 1 magnetic coils and 15 magnetic flux loos. Figures 7 show the results calculated by using a Cauchy condition (both Dirichlet and Neumann conditions) on a hyothetical surface. From Fig. 7(d), because R 0 is almost constant and S changes a little, lasma column hardly moves in the initial hase of current quench. In Fig. 7(b), since the lasma internal inductance l i is decrease raidly around at t = sec, the current density rofile becomes flat at thermal quench. This result is consistent of the measurement of T e using ECE systems as Fig. 1(c). After the flatting of current density rofile, it is found that l i much (a) (b) (c) (d) FIG. 7. The evolution of (a) lasma current, (b) lasma internal and inductance,(c) lasma internal and external inductance and (d) lasma cross-section and major radius evaluated by CCS method.

6 6 EX/7-Rc increases in time. This result is also consistent of ECE measurement results because T e rofile changes eaked rofile in Fig.1 (c). In Fig. 7(c), the lasma internal and external inductance is calculated by following equations, L i = µ 0R0li /, (8) L e = µ 0R0 ( ln8r0 / a ), (9) where a is the lasma minor radius. It is found that time change rate of L i is much larger than that of L e and time change rate of L is mainly determined by that of L i. Figure 8 shows the comarison of absolute value of R, L and time change rate of L in the initial hase of current quench. The R and L are calculated by R = πr 0 η /S and L = L i + L e, resectively and these values are time averaged values during initial hase of current quench. It is found that the absolute value of time change rate of L is the same order of magnitude as that of R or much larger than R in the short current decay time region. In addition, the exerimental current decay time is deendent on the time change rate of L. Therefore, it is necessary that the time change rate of L is taken into account in the circuit equation in order to accurately redict the current decay time in the initial hase of current quench Current Decay Model during Initial Phase of Current Quench From Eq. with V ex = 0, we obtain the following equation: I & L& / + R =. (10) I L To simlify the equation, if L & = L / t, R and L is constant in time, the rediction current decay time τ model can be reresented by τ L model = L / t + R. (11) Figure 9 shows the comarison of rediction times, which are calculated by L/R model and Eq. 11, and exerimental time. As FIG. 8. The lasma resistance R, the lasma inductance L and the time change rate of the lasma inductance as a function of current decay time. FIG.9. The comarison of the exerimental value and the model rediction value of current decay time in initial hase of current quench. shown in Fig.8, although is τ L/R much larger than the exerimental decay time in the short decay time region, τ model is same order of magnitude as exerimental decay time in some disrutive discharges and exerimental decay time increases with τ model. The time evolution of lasma inductance is almost determined by the change rate of lasma internal inductance. The above result indicates that the change rate of the lasma internal inductance associated with current rofile lays a key role to redict the recise current decay time during initial hase of current quench in JT-60U radiation induced disrutive lasmas. Here it should be noted the absolute value of τ model is not quite same as that of the exerimental decay time in Fig. 9. This result is mainly from an estimation error of lasma inductance because the

7 7 EX/7-Rc deendency of exerimental decay time on T e would be smaller than that on time change rate of L. As the candidate of the estimation error of inductance, the neglect of the eddy current during current quench in the CCS method should be considered in near future. 4. Summary We have investigated the current decay time using the initial hase of JT-60U radiation induced disrutive discharges exerimentally. The lasma resistance is estimated by ECE diagnostic systems and He I emission intensity ratios and the lasma inductance is calculated by CCS method using magnetic sensor signals. It is exerimentally confirmed that the areanormalized decay time in initial hase of current quench is indeendent of the electron temerature and decay time calculated from L/R model is larger than the exerimental decay time. This result indicates that the lasma inductance greatly changes in time. The time change rate of lasma inductance estimated by CCS method is the same order of magnitude as lasma resistance or much larger than lasma resistance. So, we consider a new model of the current decay time, which is taking the time evolution of the lasma inductance into account in the circuit equation. The rediction of the current decay time redicted by the new model is strongly deendent on the exerimental time and these absolute values are almost same. Therefore, the change rate of the lasma internal inductance lays a key role to redict the recise current decay time during initial hase of current quench in JT-60U tokamak. Here, it should be noted the new rediction value is not quite same as the exerimental value. As the reason of this result, the neglect of the eddy current during current quench in the CCS method is considered. As the future works, we should imrove the CCS method by taking the eddy current effect into account and make sure the validity of the CCS method through the direct measurement of the current rofile like the MSE. In this aer, we have just investigated the validity of L/R model. As a next ste, we should investigate what dominate the time change rate of the lasma inductance. This is one of our future subjects. References [1] Kurihara K., Fusion Eng. Des., 51-5 (000) [] Masaki K., Ando T., Kodama K., Arai T. et al., J. Nucl. Mater. 0- (1995) 390. [3] Progress in the ITER Physical Basis, Nuclear Fusion 47 (007) S171. [4] Wesley J.C., Hyatt A.W., Strait E. J. and Schissel D. P. et al., Proceedings of 1st IAEA Fusion Energy Conference, Chengdu, 16-1 Oct. (006) IT/P1-1. [5] Whyte D.G., Humhrevs D.A. and Taylor P. L., Phys. Plasma 19 (000) 405. [6] Humhrevs D.A. and Whyte D.G., Phys. Plasma 19 (000) [7] Kubo H., Goto M. and Takenaga H. et al., J. Plasma and Fusion Res., 75 (1999) 945. [8] Kajita S., Ohno N. and Takamura S. et al., Physics of Plasmas, 13 (006) [9] Okamoto M., Ohno N. and Takamura S., J. Plasma and Fusion Res., 3 (008) [10] Sitzer L. and Härm R., Physical Review 89 (1953) 977. [11] Arnaud M., Rohtenflug R., Astron. Astrohys. Sul. Ser. 60 (1985) 45.

Role of the Electron Temperature in the Current Decay during Disruption in JT-60U )

Role of the Electron Temperature in the Current Decay during Disruption in JT-60U ) Role of the Electron Temperature in the Current Decay during Disruption in JT-60U ) Yoshihide SHIBATA, Akihiko ISAYAMA, Go MATSUNAGA, Yasunori KAWANO, Seiji MIYAMOTO 1), Victor LUKASH 2), Rustam KHAYRUTDINOV

More information

Pellet fuelling of plasmas with ELM mitigation by resonant magnetic perturbations in MAST

Pellet fuelling of plasmas with ELM mitigation by resonant magnetic perturbations in MAST 1 Pellet fuelling of lasmas with mitigation by resonant magnetic erturbations in MAST M Valovič, G Cunningham, L Garzotti, C Gurl, A Kirk, G Naylor, A Patel, R Scannell, A J Thornton and the MAST team

More information

Wave Form of Current Quench during Disruptions in Tokamaks

Wave Form of Current Quench during Disruptions in Tokamaks Wave Form of Current Quench during Disruptions in Tokamaks SUGIHARA Masayoshi, LUKASH Victor 1), KAWANO Yasunori 2), YOSHINO Ryuji 2), GRIBOV Yuri, KHAYRUTDINOV Rustam 3), MIKI Nobuharu 2), OHMORI Junji

More information

0 Magnetically Confined Plasma

0 Magnetically Confined Plasma 0 Magnetically Confined Plasma 0.1 Particle Motion in Prescribed Fields The equation of motion for species s (= e, i) is written as d v ( s m s dt = q s E + vs B). The motion in a constant magnetic field

More information

Evolution of Bootstrap-Sustained Discharge in JT-60U

Evolution of Bootstrap-Sustained Discharge in JT-60U EX1-4 Evolution of Bootstrap-Sustained Discharge in JT-60U Y. Takase, a S. Ide, b Y. Kamada, b H. Kubo, b O. Mitarai, c H. Nuga, a Y. Sakamoto, b T. Suzuki, b H. Takenaga, b and the JT-60 Team a University

More information

16. CHARACTERISTICS OF SHOCK-WAVE UNDER LORENTZ FORCE AND ENERGY EXCHANGE

16. CHARACTERISTICS OF SHOCK-WAVE UNDER LORENTZ FORCE AND ENERGY EXCHANGE 16. CHARACTERISTICS OF SHOCK-WAVE UNDER LORENTZ FORCE AND ENERGY EXCHANGE H. Yamasaki, M. Abe and Y. Okuno Graduate School at Nagatsuta, Tokyo Institute of Technology 459, Nagatsuta, Midori-ku, Yokohama,

More information

PREDICTIVE MODELING OF PLASMA HALO EVOLUTION IN POST-THERMAL QUENCH DISRUPTING PLASMAS

PREDICTIVE MODELING OF PLASMA HALO EVOLUTION IN POST-THERMAL QUENCH DISRUPTING PLASMAS GA A25488 PREDICTIVE MODELING OF PLASMA HALO EVOLUTION IN POST-THERMAL QUENCH DISRUPTING PLASMAS by D.A. HUMPHREYS, D.G. WHYTE, M. BAKHTIARI, R.D. DERANIAN, E.M. HOLLMANN, A.W. HYATT, T.C. JERNIGAN, A.G.

More information

dn i where we have used the Gibbs equation for the Gibbs energy and the definition of chemical potential

dn i where we have used the Gibbs equation for the Gibbs energy and the definition of chemical potential Chem 467 Sulement to Lectures 33 Phase Equilibrium Chemical Potential Revisited We introduced the chemical otential as the conjugate variable to amount. Briefly reviewing, the total Gibbs energy of a system

More information

University of North Carolina-Charlotte Department of Electrical and Computer Engineering ECGR 4143/5195 Electrical Machinery Fall 2009

University of North Carolina-Charlotte Department of Electrical and Computer Engineering ECGR 4143/5195 Electrical Machinery Fall 2009 University of North Carolina-Charlotte Deartment of Electrical and Comuter Engineering ECG 4143/5195 Electrical Machinery Fall 9 Problem Set 5 Part Due: Friday October 3 Problem 3: Modeling the exerimental

More information

EX/C3-5Rb Relationship between particle and heat transport in JT-60U plasmas with internal transport barrier

EX/C3-5Rb Relationship between particle and heat transport in JT-60U plasmas with internal transport barrier EX/C-Rb Relationship between particle and heat transport in JT-U plasmas with internal transport barrier H. Takenaga ), S. Higashijima ), N. Oyama ), L. G. Bruskin ), Y. Koide ), S. Ide ), H. Shirai ),

More information

Design Constraint for Fine Grain Supply Voltage Control LSI

Design Constraint for Fine Grain Supply Voltage Control LSI ASP-DAC 211 Designer s Forum Session 8D-3: State-of-The-Art SoCs and Design Methodologies Design Constraint for Fine Grain Suly Voltage Control LSI January 28, 211 Atsuki Inoue Platform Technologies Laboratories

More information

1 EX/P6-5 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation

1 EX/P6-5 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation 1 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation Y. Nakashima1), Y. Higashizono1), H. Kawano1), H. Takenaga2), N. Asakura2), N. Oyama2),

More information

Modelling of JT-60U Detached Divertor Plasma using SONIC code

Modelling of JT-60U Detached Divertor Plasma using SONIC code J. Plasma Fusion Res. SERIES, Vol. 9 (2010) Modelling of JT-60U Detached Divertor Plasma using SONIC code Kazuo HOSHINO, Katsuhiro SHIMIZU, Tomonori TAKIZUKA, Nobuyuki ASAKURA and Tomohide NAKANO Japan

More information

22.615, MHD Theory of Fusion Systems Prof. Freidberg Lecture 13: PF Design II The Coil Solver

22.615, MHD Theory of Fusion Systems Prof. Freidberg Lecture 13: PF Design II The Coil Solver .615, MHD Theory of Fusion Systems Prof. Freidberg Lecture 13: PF Design II The Coil Solver Introduction 1. Let us assume that we have successfully solved the Grad Shafranov equation for a fixed boundary

More information

Magnetic Field Configuration Dependence of Plasma Production and Parallel Transport in a Linear Plasma Device NUMBER )

Magnetic Field Configuration Dependence of Plasma Production and Parallel Transport in a Linear Plasma Device NUMBER ) Magnetic Field Configuration Dependence of Plasma Production and Parallel Transport in a Linear Plasma Device NUMBER ) Daichi HAMADA, Atsushi OKAMOTO, Takaaki FUJITA, Hideki ARIMOTO, Katsuya SATOU and

More information

Invariant yield calculation

Invariant yield calculation Chater 6 Invariant yield calculation he invariant yield of the neutral ions and η mesons er one minimum bias collision as a function of the transverse momentum is given by E d3 N d 3 = d 3 N d dydφ = d

More information

Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas )

Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas ) Comparison of Ion Internal Transport Barrier Formation between Hydrogen and Helium Dominated Plasmas ) Kenichi NAGAOKA 1,2), Hiromi TAKAHASHI 1,2), Kenji TANAKA 1), Masaki OSAKABE 1,2), Sadayoshi MURAKAMI

More information

Evolution of Bootstrap-Sustained Discharge in JT-60U

Evolution of Bootstrap-Sustained Discharge in JT-60U 1 Evolution of Bootstrap-Sustained Discharge in JT-60U Y. Takase 1), S. Ide 2), Y. Kamada 2), H. Kubo 2), O. Mitarai 3), H. Nuga 1), Y. Sakamoto 2), T. Suzuki 2), H. Takenaga 2), and the JT-60 Team 1)

More information

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science Recent Development of LHD Experiment O.Motojima for the LHD team National Institute for Fusion Science 4521 1 Primary goal of LHD project 1. Transport studies in sufficiently high n E T regime relevant

More information

Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U

Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U EX/D-3 Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-6U N. Asakura ), H. Takenaga ), S. Sakurai ), G.D. Porter ), T.D. Rognlien ), M.E. Rensink ), O. Naito ), K. Shimizu

More information

Non-disruptive MHD Dynamics in Inward-shifted LHD Configurations

Non-disruptive MHD Dynamics in Inward-shifted LHD Configurations Non-disrutive MHD Dynamics in Inward-shifted LHD Configurations.Introduction.MHD simulation 3.DNS of full 3D MHD 4. Summary MIUA H. ICHIGUCHI K. NAKAJIMA N. HAYASHI T. (National Institute for Fusion Science)

More information

- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation -

- Effect of Stochastic Field and Resonant Magnetic Perturbation on Global MHD Fluctuation - 15TH WORKSHOP ON MHD STABILITY CONTROL: "US-Japan Workshop on 3D Magnetic Field Effects in MHD Control" U. Wisconsin, Madison, Nov 15-17, 17, 2010 LHD experiments relevant to Tokamak MHD control - Effect

More information

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas )

Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas ) Formation and Long Term Evolution of an Externally Driven Magnetic Island in Rotating Plasmas ) Yasutomo ISHII and Andrei SMOLYAKOV 1) Japan Atomic Energy Agency, Ibaraki 311-0102, Japan 1) University

More information

Design of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system

Design of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system Design of next step tokamak: Consistent analysis of plasma flux consumption and poloidal field system J.M. Ané 1, V. Grandgirard, F. Albajar 1, J.Johner 1 1Euratom-CEA Association, Cadarache, France Euratom-EPFL

More information

arxiv:cond-mat/ v2 25 Sep 2002

arxiv:cond-mat/ v2 25 Sep 2002 Energy fluctuations at the multicritical oint in two-dimensional sin glasses arxiv:cond-mat/0207694 v2 25 Se 2002 1. Introduction Hidetoshi Nishimori, Cyril Falvo and Yukiyasu Ozeki Deartment of Physics,

More information

Velocity Changing and Dephasing collisions Effect on electromagnetically induced transparency in V-type Three level Atomic System.

Velocity Changing and Dephasing collisions Effect on electromagnetically induced transparency in V-type Three level Atomic System. Velocity Changing and Dehasing collisions Effect on electromagnetically induced transarency in V-tye Three level Atomic System. Anil Kumar M. and Suneel Singh University of Hyderabad, School of hysics,

More information

Influence of Plasma Opacity on Current Decay after Disruptions in Tokamaks

Influence of Plasma Opacity on Current Decay after Disruptions in Tokamaks 1 Influence of Plasma Opacity on Current Decay after Disruptions in Tokamaks V.E Lukash 1), A.B. Mineev 2), and D.Kh. Morozov 1) 1) Institute of Nuclear Fusion, RRC Kurchatov Institute, Moscow, Russia

More information

Speed of sound measurements in liquid Methane at cryogenic temperature and for pressure up to 10 MPa

Speed of sound measurements in liquid Methane at cryogenic temperature and for pressure up to 10 MPa LNGII - raining Day Delft, August 07 Seed of sound measurements in liquid Methane at cryogenic temerature and for ressure u to 0 MPa Simona Lago*, P. Alberto Giuliano Albo INRiM Istituto Nazionale di Ricerca

More information

Structure of 11 Be studied in β-delayed neutron- and γ- decay from polarized 11 Li

Structure of 11 Be studied in β-delayed neutron- and γ- decay from polarized 11 Li Nuclear Physics A 46 (4) c c Structure of Be studied in β-delayed neutron- and γ- decay from olarized Li Y. Hirayama a, T. Shimoda a,h.izumi a,h.yano a,m.yagi a, A. Hatakeyama b, C.D.P. Levy c,k.p.jackson

More information

EVALUATION OF THE THEORETICAL ERROR FOR THE LIGHTNING PEAK CURRENT AS MEASURED BY LIGHTNING LOCATION SYSTEMS

EVALUATION OF THE THEORETICAL ERROR FOR THE LIGHTNING PEAK CURRENT AS MEASURED BY LIGHTNING LOCATION SYSTEMS X nternational Symosium on Lightning Protection 6 th -30 th Novemer 007 Foz do guaçu, razil EVALUATON OF THE THEORETCAL ERROR FOR THE LGHTNNG PEAK CURRENT AS MEASURE Y LGHTNNG LOCATON SYSTEMS Cinzia Rovelli

More information

An Improved Calibration Method for a Chopped Pyrgeometer

An Improved Calibration Method for a Chopped Pyrgeometer 96 JOURNAL OF ATMOSPHERIC AND OCEANIC TECHNOLOGY VOLUME 17 An Imroved Calibration Method for a Choed Pyrgeometer FRIEDRICH FERGG OtoLab, Ingenieurbüro, Munich, Germany PETER WENDLING Deutsches Forschungszentrum

More information

Pressure-sensitivity Effects on Toughness Measurements of Compact Tension Specimens for Strain-hardening Solids

Pressure-sensitivity Effects on Toughness Measurements of Compact Tension Specimens for Strain-hardening Solids American Journal of Alied Sciences (9): 19-195, 5 ISSN 1546-939 5 Science Publications Pressure-sensitivity Effects on Toughness Measurements of Comact Tension Secimens for Strain-hardening Solids Abdulhamid

More information

Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology

Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology th IEEE/NPSS Symposium on Fusion Engineering (SOFE) October 14-17, 3, San Diego, CA USA Plasma Production in a Small High Field Force-alanced Coil Tokamak ased on Virial Theorem H.Tsutsui, T.Ito, H.Ajikawa,

More information

Physics of fusion power. Lecture 14: Anomalous transport / ITER

Physics of fusion power. Lecture 14: Anomalous transport / ITER Physics of fusion power Lecture 14: Anomalous transport / ITER Thursday.. Guest lecturer and international celebrity Dr. D. Gericke will give an overview of inertial confinement fusion.. Instabilities

More information

Optical self-energy of superconducting Pb in the terahertz region

Optical self-energy of superconducting Pb in the terahertz region Otical self-energy of suerconducting Pb in the terahertz region T. Mori, 1 E. J. Nicol, 2, * S. Shiizuka, 1 K. Kuniyasu, 3 T. Nojima, 3 N. Toyota, 1 and J. P. Carbotte 4 1 Physics Deartment, Graduate School

More information

Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak

Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak 1 EXS/P2-19 Double Null Merging Start-up Experiments in the University of Tokyo Spherical Tokamak T. Yamada 1), R. Imazawa 2), S. Kamio 1), R. Hihara 1), K. Abe 1), M. Sakumura 1), Q. H. Cao 1), H. Sakakita

More information

Study on the Electromagnetic Force Affected by Short-Circuit Current in Vertical and Horizontal Arrangement of Busbar System

Study on the Electromagnetic Force Affected by Short-Circuit Current in Vertical and Horizontal Arrangement of Busbar System International Conference on Electrical, Control and Comuter Engineering Pahang, Malaysia, June 1-, 011 Study on the Electromagnetic Force Affected by Short-Circuit Current in Vertical and Horizontal Arrangement

More information

Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device

Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device Kenichi NAGAOKA, Masayuki YOKOYAMA, Yasuhiko TAKEIRI, Katsumi IDA, Mikiro YOSHINUMA, Seikichi MATSUOKA 1),

More information

Study of Current drive efficiency and its correlation with photon temperature in the HT-7 tokomak

Study of Current drive efficiency and its correlation with photon temperature in the HT-7 tokomak Study of Current drive efficiency and its correlation with photon temperature in the HT-7 tokomak Dr. Jawad Younis Senior Scientist Pakistan Atomic Energy Commission, P. O. Box, 2151,Islamabad Institute

More information

PHYSICAL REVIEW LETTERS

PHYSICAL REVIEW LETTERS PHYSICAL REVIEW LETTERS VOLUME 80 29 JUNE 1998 NUMBER 26 Heavy Meson Decay Constants from Quenched Lattice QCD S. Aoki, 1, * M. Fukugita, 2 S. Hashimoto, 3, N. Ishizuka, 1,4 Y. Iwasaki, 1,4 K. Kanaya,

More information

YIELD OF SECONDARY ELECTRON EMISSION FROM CERAMIC MATERIALS OF HALL THRUSTER WITH SEGMENTED ELECTRODES

YIELD OF SECONDARY ELECTRON EMISSION FROM CERAMIC MATERIALS OF HALL THRUSTER WITH SEGMENTED ELECTRODES YELD OF SECONDARY ELECTRON EMSSON FROM CERAMC MATERALS OF HALL THRUSTER WTH SEGMENTED ELECTRODES A. Dunaevsky, Y. Raitses, and N. J. Fisch Plasma Physics Laboratory, Princeton University, P.O.Box 451,

More information

Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-60U

Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-60U 1 EX/P4-25 Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-6U T. Nakano, H. Kubo, N. Asakura, K. Shimizu and S. Higashijima Japan Atomic Energy Agency, Naka,

More information

Dynamics of ion internal transport barrier in LHD heliotron and JT-60U tokamak plasmas

Dynamics of ion internal transport barrier in LHD heliotron and JT-60U tokamak plasmas Dynamics of ion internal transport barrier in LHD heliotron and JT-60U tokamak plasmas K. Ida 1), Y. Sakamoto 2), M. Yoshinuma 1), H. Takenaga 2), K. Nagaoka 1), N. Oyama 2), M. Osakabe 1), M. Yokoyama

More information

Maximum Entropy and the Stress Distribution in Soft Disk Packings Above Jamming

Maximum Entropy and the Stress Distribution in Soft Disk Packings Above Jamming Maximum Entroy and the Stress Distribution in Soft Disk Packings Above Jamming Yegang Wu and S. Teitel Deartment of Physics and Astronomy, University of ochester, ochester, New York 467, USA (Dated: August

More information

Advanced Tokamak Research in JT-60U and JT-60SA

Advanced Tokamak Research in JT-60U and JT-60SA I-07 Advanced Tokamak Research in and JT-60SA A. Isayama for the JT-60 team 18th International Toki Conference (ITC18) December 9-12, 2008 Ceratopia Toki, Toki Gifu JAPAN Contents Advanced tokamak development

More information

Casimir Force Between the Two Moving Conductive Plates.

Casimir Force Between the Two Moving Conductive Plates. Casimir Force Between the Two Moving Conductive Plates. Jaroslav Hynecek 1 Isetex, Inc., 95 Pama Drive, Allen, TX 751 ABSTRACT This article resents the derivation of the Casimir force for the two moving

More information

High speed wind tunnels 2.0 Definition of high speed. 2.1 Types of high speed wind tunnels

High speed wind tunnels 2.0 Definition of high speed. 2.1 Types of high speed wind tunnels Module Lectures 6 to 1 High Seed Wind Tunnels Keywords: Blow down wind tunnels, Indraft wind tunnels, suersonic wind tunnels, c-d nozzles, second throat diffuser, shocks, condensation in wind tunnels,

More information

STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-60U

STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-60U Abstract STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-6U A. SAKASAI, H. TAKENAGA, N. HOSOGANE, H. KUBO, S. SAKURAI, N. AKINO, T. FUJITA, S. HIGASHIJIMA, H. TAMAI, N. ASAKURA, K. ITAMI,

More information

Heating and Current Drive by Electron Cyclotron Waves in JT-60U

Heating and Current Drive by Electron Cyclotron Waves in JT-60U EX/W- Heating and Current Drive by Electron Cyclotron Waves in JT-6U T. Suzuki ), S. Ide ), C. C. Petty ), Y. Ikeda ), K. Kajiwara ), A. Isayama ), K. Hamamatsu ), O. Naito ), M. Seki ), S. Moriyama )

More information

Resistive Wall Mode Control in DIII-D

Resistive Wall Mode Control in DIII-D Resistive Wall Mode Control in DIII-D by Andrea M. Garofalo 1 for G.L. Jackson 2, R.J. La Haye 2, M. Okabayashi 3, H. Reimerdes 1, E.J. Strait 2, R.J. Groebner 2, Y. In 4, M.J. Lanctot 1, G.A. Navratil

More information

EE 508 Lecture 13. Statistical Characterization of Filter Characteristics

EE 508 Lecture 13. Statistical Characterization of Filter Characteristics EE 508 Lecture 3 Statistical Characterization of Filter Characteristics Comonents used to build filters are not recisely redictable L C Temerature Variations Manufacturing Variations Aging Model variations

More information

An Investigation on the Numerical Ill-conditioning of Hybrid State Estimators

An Investigation on the Numerical Ill-conditioning of Hybrid State Estimators An Investigation on the Numerical Ill-conditioning of Hybrid State Estimators S. K. Mallik, Student Member, IEEE, S. Chakrabarti, Senior Member, IEEE, S. N. Singh, Senior Member, IEEE Deartment of Electrical

More information

DT Fusion Ignition of LHD-Type Helical Reactor by Joule Heating Associated with Magnetic Axis Shift )

DT Fusion Ignition of LHD-Type Helical Reactor by Joule Heating Associated with Magnetic Axis Shift ) DT Fusion Ignition of LHD-Type Helical Reactor by Joule Heating Associated with Magnetic Axis Shift ) Tsuguhiro WATANABE National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Japan (Received

More information

MODELING THE RELIABILITY OF C4ISR SYSTEMS HARDWARE/SOFTWARE COMPONENTS USING AN IMPROVED MARKOV MODEL

MODELING THE RELIABILITY OF C4ISR SYSTEMS HARDWARE/SOFTWARE COMPONENTS USING AN IMPROVED MARKOV MODEL Technical Sciences and Alied Mathematics MODELING THE RELIABILITY OF CISR SYSTEMS HARDWARE/SOFTWARE COMPONENTS USING AN IMPROVED MARKOV MODEL Cezar VASILESCU Regional Deartment of Defense Resources Management

More information

arxiv: v1 [nucl-ex] 28 Sep 2009

arxiv: v1 [nucl-ex] 28 Sep 2009 Raidity losses in heavy-ion collisions from AGS to RHIC energies arxiv:99.546v1 [nucl-ex] 28 Se 29 1. Introduction F. C. Zhou 1,2, Z. B. Yin 1,2 and D. C. Zhou 1,2 1 Institute of Particle Physics, Huazhong

More information

Lecture contents. Metals: Drude model Conductivity frequency dependence Plasma waves Difficulties of classical free electron model

Lecture contents. Metals: Drude model Conductivity frequency dependence Plasma waves Difficulties of classical free electron model Lecture contents Metals: Drude model Conductivity frequency deendence Plasma waves Difficulties of classical free electron model Paul Karl Ludwig Drude (German: [ˈdʀuːdə]; July, 863 July 5, 96) Phenomenology

More information

Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod

Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod 1 EX/P4-22 Characterization of neo-classical tearing modes in high-performance I- mode plasmas with ICRF mode conversion flow drive on Alcator C-Mod Y. Lin, R.S. Granetz, A.E. Hubbard, M.L. Reinke, J.E.

More information

Available online at ScienceDirect. Procedia Engineering 102 (2015 )

Available online at  ScienceDirect. Procedia Engineering 102 (2015 ) Available online at www.sciencedirect.com ScienceDirect Procedia Engineering 1 (15 ) 3 38 The 7th World Congress on Particle Technology (WCPT7) Characterization of Colloidal Particles using Electrical

More information

Factors Effect on the Saturation Parameter S and there Influences on the Gain Behavior of Ytterbium Doped Fiber Amplifier

Factors Effect on the Saturation Parameter S and there Influences on the Gain Behavior of Ytterbium Doped Fiber Amplifier Australian Journal of Basic and Alied Sciences, 5(12): 2010-2020, 2011 ISSN 1991-8178 Factors Effect on the Saturation Parameter S and there Influences on the Gain Behavior of Ytterbium Doed Fiber Amlifier

More information

Bunno, M.; Nakamura, Y.; Suzuki, Y. Matsunaga, G.; Tani, K. Citation Plasma Science and Technology (

Bunno, M.; Nakamura, Y.; Suzuki, Y. Matsunaga, G.; Tani, K. Citation Plasma Science and Technology ( Title The Finite Beta Effects on the Toro Tokamak Plasma Author(s) Bunno, M.; Nakamura, Y.; Suzuki, Y. Matsunaga, G.; Tani, K. Citation Plasma Science and Technology (2013 Issue Date 2013-02 URL http://hdl.handle.net/2433/173038

More information

PHYSICAL REVIEW LETTERS

PHYSICAL REVIEW LETTERS PHYSICAL REVIEW LETTERS VOLUME 81 20 JULY 1998 NUMBER 3 Searated-Path Ramsey Atom Interferometer P. D. Featonby, G. S. Summy, C. L. Webb, R. M. Godun, M. K. Oberthaler, A. C. Wilson, C. J. Foot, and K.

More information

Discharge initiation and plasma column formation in aspect ratio A=2 tokamak.

Discharge initiation and plasma column formation in aspect ratio A=2 tokamak. Discharge initiation an lasma column formation in asect ratio A toama... Khayrutinov E.A. Azizov, A.D. Baralov, G.G.Glaush, I.L.Taibaeva, Ph.W.West 3 Troits, Moscow eg., ussia NNC, K 3 General Atomics,

More information

Bifurcation-Like Behavior of Electrostatic Potential in LHD )

Bifurcation-Like Behavior of Electrostatic Potential in LHD ) Bifurcation-Like Behavior of Electrostatic Potential in LHD ) Akihiro SHIMIZU, Takeshi IDO, Masaki NISHIURA, Ryohei MAKINO 1), Masayuki YOKOYAMA, Hiromi TAKAHASHI, Hiroe IGAMI, Yasuo YOSHIMURA, Shin KUBO,

More information

The extreme case of the anisothermal calorimeter when there is no heat exchange is the adiabatic calorimeter.

The extreme case of the anisothermal calorimeter when there is no heat exchange is the adiabatic calorimeter. .4. Determination of the enthaly of solution of anhydrous and hydrous sodium acetate by anisothermal calorimeter, and the enthaly of melting of ice by isothermal heat flow calorimeter Theoretical background

More information

TSC modelling of major disruption and VDE events in NSTX and ASDEX- Upgrade and predictions for ITER

TSC modelling of major disruption and VDE events in NSTX and ASDEX- Upgrade and predictions for ITER ITR/P1-16 TSC modelling of major disruption and VDE events in NSTX and ASDEX- Upgrade and predictions for ITER I. Bandyopadhyay 1), S. Gerhardt 2), S. C. Jardin 2), R.O. Sayer 3), Y. Nakamura 4), S. Miyamoto

More information

Disruption Mitigation on Tore Supra

Disruption Mitigation on Tore Supra 1 EX/1-6Rc Disruption Mitigation on Tore Supra G. Martin, F. Sourd, F. Saint-Laurent, J. Bucalossi, L.G. Eriksson Association Euratom-CEA, DRFC/STEP, CEA/Cadarache F-1318 SAINT PAUL LEZ DURANCE / FRANCE

More information

Plasma models for the design of the ITER PCS

Plasma models for the design of the ITER PCS Plasma models for the design of the ITER PCS G. De Tommasi 1,2 on behalf of the CREATE team 1 Consorzio CREATE, Naples, Italy 2 Department of Electrical Engineering and Information Technology, University

More information

ANALYTICAL MODEL FOR THE BYPASS VALVE IN A LOOP HEAT PIPE

ANALYTICAL MODEL FOR THE BYPASS VALVE IN A LOOP HEAT PIPE ANALYTICAL MODEL FOR THE BYPASS ALE IN A LOOP HEAT PIPE Michel Seetjens & Camilo Rindt Laboratory for Energy Technology Mechanical Engineering Deartment Eindhoven University of Technology The Netherlands

More information

Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 )

Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 ) Experimental Study of Hall Effect on a Formation Process of an FRC by Counter-Helicity Spheromak Merging in TS-4 ) Yasuhiro KAMINOU, Michiaki INOMOTO and Yasushi ONO Graduate School of Engineering, The

More information

D- 3 He HA tokamak device for experiments and power generations

D- 3 He HA tokamak device for experiments and power generations D- He HA tokamak device for experiments and power generations US-Japan Fusion Power Plant Studies Contents University of Tokyo, Japan January -, 5 O.Mitarai (Kyushu Tokai University).Motivation.Formalism,

More information

pp physics, RWTH, WS 2003/04, T.Hebbeker

pp physics, RWTH, WS 2003/04, T.Hebbeker 1. PP TH 03/04 Accelerators and Detectors 1 hysics, RWTH, WS 2003/04, T.Hebbeker 2003-12-03 1. Accelerators and Detectors In the following, we concentrate on the three machines SPS, Tevatron and LHC with

More information

RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER

RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER GA A24759 RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER by A.M. GAROFALO, J. BIALEK, M.S. CHANCE, M.S. CHU, D.H. EDGELL, G.L. JACKSON, T.H. JENSEN, R.J.

More information

DIII-D TOKAMAK MODELING OF THE RECYCLING PARTICLE FLUX AND ELECTRON PARTICLE TRANSPORT IN THE

DIII-D TOKAMAK MODELING OF THE RECYCLING PARTICLE FLUX AND ELECTRON PARTICLE TRANSPORT IN THE MODELING OF THE RECYCLING ARTICLE FLUX AND ELECTRON ARTICLE TRANSORT IN THE DIIID TOKAMAK by D.R. BAKER, R. MAINGI, L.W. OWEN, G.D. ORTER, and G.L. JACKSON OCTOBER 1996 GENERAL ATOMICS ortions of this

More information

Focused azimuthally polarized vector beam and spatial magnetic resolution below the diffraction limit

Focused azimuthally polarized vector beam and spatial magnetic resolution below the diffraction limit Research Article Vol. 33, No. 11 / November 2016 / Journal of the Otical Society of America B 2265 Focused azimuthally olarized vector beam and satial magnetic resolution below the diffraction limit MEHDI

More information

CFD AS A DESIGN TOOL FOR FLUID POWER COMPONENTS

CFD AS A DESIGN TOOL FOR FLUID POWER COMPONENTS CFD AS A DESIGN TOOL FOR FLUID POWER COMPONENTS M. BORGHI - M. MILANI Diartimento di Scienze dell Ingegneria Università degli Studi di Modena Via Cami, 213/b 41100 Modena E-mail: borghi@omero.dsi.unimo.it

More information

Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport

Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport 1 Integrated Simulation of ELM Energy Loss Determined by Pedestal MHD and SOL Transport N. Hayashi, T. Takizuka, T. Ozeki, N. Aiba, N. Oyama Japan Atomic Energy Agency, Naka, Ibaraki-ken, 311-0193 Japan

More information

Equilibrium and transport in Tokamaks

Equilibrium and transport in Tokamaks Equilibrium and transport in Tokamaks Jacques Blum Laboratoire J.-A. Dieudonné, Université de Nice Sophia-Antipolis Parc Valrose 06108 Nice Cedex 02, France jblum@unice.fr 08 septembre 2008 Jacques Blum

More information

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE 1 EX/P6-18 Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE M. Uchida, T. Maekawa, H. Tanaka, F. Watanabe, Y.

More information

Toward the Realization of Fusion Energy

Toward the Realization of Fusion Energy Toward the Realization of Fusion Energy Nuclear fusion is the energy source of the sun and stars, in which light atomic nuclei fuse together, releasing a large amount of energy. Fusion power can be generated

More information

PROCESSING OF LOW-VISCOSITY CBT THERMOPLASTIC COMPOSITES: HEAT TRANSFER ANALYSIS

PROCESSING OF LOW-VISCOSITY CBT THERMOPLASTIC COMPOSITES: HEAT TRANSFER ANALYSIS PROCESSING OF LOW-VISCOSITY CBT THERMOPLASTIC COMPOSITES: HEAT TRANSFER ANALYSIS Dr. Adrian Murtagh, Siora Coll and Dr. Conchúr Ó Brádaigh Comosites Research Unit Det. of Mechanical & Biomedical Engineering,

More information

Modelling of non-uniform DC driven glow discharge in argon gas

Modelling of non-uniform DC driven glow discharge in argon gas Physics Letters A 367 (2007) 114 119 www.elsevier.com/locate/la Modelling of non-uniform DC driven glow discharge in argon gas I.R. Rafatov,1, D. Akbar, S. Bilikmen Physics Deartment, Middle East Technical

More information

Polarization Mode Dispersion Mitigation through Spun Fibers

Polarization Mode Dispersion Mitigation through Spun Fibers INTERNATIONAL JOURNAL O MICROWAVE AND OPTICAL TECHNOLOGY, 176 VOL.5 NO.3 MAY 1 Polarization Mode Disersion Mitigation through Sun ibers Dowluru Ravi Kumar*, Dr.. Prabhakara Rao * Lecturer in ECE, Deartment

More information

FUGACITY. It is simply a measure of molar Gibbs energy of a real gas.

FUGACITY. It is simply a measure of molar Gibbs energy of a real gas. FUGACITY It is simly a measure of molar Gibbs energy of a real gas. Modifying the simle equation for the chemical otential of an ideal gas by introducing the concet of a fugacity (f). The fugacity is an

More information

Estimating the plasma flow in a recombining plasma from

Estimating the plasma flow in a recombining plasma from Paper P3-38 Estimating the plasma flow in a recombining plasma from the H α emission U. Wenzel a, M. Goto b a Max-Planck-Institut für Plasmaphysik (IPP) b National Institute for Fusion Science, Toki 509-5292,

More information

Transport at surface nanostructures measured by four-tip STM q

Transport at surface nanostructures measured by four-tip STM q Current Alied Physics 2 (2002) 465 471 www.elsevier.com/locate/ca Transort at surface nanostructures measured by four-ti STM q Shuji Hasegawa *, Ichiro Shiraki, Fuhito Tanabe, Rei Hobara Deartment of Physics,

More information

Physics and Engineering Studies of the Advanced Divertor for a Fusion Reactor

Physics and Engineering Studies of the Advanced Divertor for a Fusion Reactor 1 FIP/3-4Ra Physics and Engineering Studies of the Advanced Divertor for a Fusion Reactor N. Asakura 1, K. Hoshino 1, H. Utoh 1, K. Shinya 2, K. Shimizu 3, S. Tokunaga 1, Y.Someya 1, K. Tobita 1, N. Ohno

More information

Current density modelling in JET and JT-60U identity plasma experiments. Paula Sirén

Current density modelling in JET and JT-60U identity plasma experiments. Paula Sirén Current density modelling in JET and JT-60U identity plasma experiments Paula Sirén 1/12 1/16 Euratom-TEKES Euratom-Tekes Annual Seminar 2013 28 24 May 2013 Paula Sirén Current density modelling in JET

More information

HIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES

HIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES HIGH PERFORMANCE EXPERIMENTS IN JT-U REVERSED SHEAR DISCHARGES IAEA-CN-9/EX/ T. FUJITA, Y. KAMADA, S. ISHIDA, Y. NEYATANI, T. OIKAWA, S. IDE, S. TAKEJI, Y. KOIDE, A. ISAYAMA, T. FUKUDA, T. HATAE, Y. ISHII,

More information

STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK

STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK GA A24738 STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK by T.C. LUCE, C.C. PETTY, D.A. HUMPHREYS, R.J. LA HAYE, and R. PRATER JULY 24 DISCLAIMER This

More information

Control of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform. Jeffrey Herfindal

Control of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform. Jeffrey Herfindal Control of Sawtooth Oscillation Dynamics using Externally Applied Stellarator Transform Jeffrey Herfindal D.A. Ennis, J.D. Hanson, G.J. Hartwell, S.F. Knowlton, X. Ma, D.A. Maurer, M.D. Pandya, N.A. Roberds,

More information

Density Collapse in Improved Confinement Mode on Tohoku University Heliac

Density Collapse in Improved Confinement Mode on Tohoku University Heliac 1 EX/P5-12 Density Collapse in Improved Confinement Mode on Tohoku University Heliac S. Kitajima 1), Y. Tanaka 2), H. Utoh 1), H. Umetsu 1), J. Sato 1), K. Ishii 1), T. Kobuchi 1), A. Okamoto 1), M. Sasao

More information

FDTD solutions for the distribution of radiation from dipoles embedded in dielectric particles

FDTD solutions for the distribution of radiation from dipoles embedded in dielectric particles Journal of Quantitative Sectroscoy & Radiative Transfer 106 (007) 57 61 www.elsevier.com/locate/jqsrt FDTD solutions for the distribution of radiation from dioles embedded in dielectric articles Changhui

More information

Fokker-Planck Simulation Study of Hot-Tail Effect on Runaway Electron Generation in ITER Disruptions )

Fokker-Planck Simulation Study of Hot-Tail Effect on Runaway Electron Generation in ITER Disruptions ) Fokker-Planck Simulation Study of Hot-Tail Effect on Runaway Electron Generation in ITER Disruptions ) Hideo NUGA, Akinobu MATSUYAMA 1), Masatoshi YAGI 1) and Atsushi FUKUYAMA Kyoto University, Kyoto-Daigaku-Katsura,

More information

Control the high-order harmonics cutoff through the. combination of chirped laser and static electric field

Control the high-order harmonics cutoff through the. combination of chirped laser and static electric field Control the high-order harmonics cutoff through the combination of chired laser and static electric field Yang Xiang,, Yueing iu Shangqing Gong State Key Laboratory of High Field Laser Physics, Shanghai

More information

International Journal of Mathematics Trends and Technology- Volume3 Issue4-2012

International Journal of Mathematics Trends and Technology- Volume3 Issue4-2012 Effect of Hall current on Unsteady Flow of a Dusty Conducting Fluid through orous medium between Parallel Porous Plates with Temerature Deendent Viscosity and Thermal Radiation Harshbardhan Singh and Dr.

More information

Simulation Study of Interaction between Energetic Ions and Alfvén Eigenmodes in LHD

Simulation Study of Interaction between Energetic Ions and Alfvén Eigenmodes in LHD 1 Simulation Study of Interaction between Energetic Ions and Alfvén Eigenmodes in LHD Y. Todo 1), N. Nakajima 1), M. Osakabe 1), S. Yamamoto 2), D. A. Spong 3) 1) National Institute for Fusion Science,

More information

(Inductive tokamak plasma initial start-up)

(Inductive tokamak plasma initial start-up) (Inductive tokamak plasma initial start-up) 24. 6. 7. (tapl1.kaist.ac.kr) Outline Conventional inductive tokamak plasma start-up Inductive outer PF coil-only plasma start-up Inductive plasma start-up in

More information

rate~ If no additional source of holes were present, the excess

rate~ If no additional source of holes were present, the excess DIFFUSION OF CARRIERS Diffusion currents are resent in semiconductor devices which generate a satially non-uniform distribution of carriers. The most imortant examles are the -n junction and the biolar

More information

Electrode Biasing Experiment in the Large Helical Device

Electrode Biasing Experiment in the Large Helical Device 1 EXC/P8-07 Electrode Biasing Experiment in the Large Helical Device S. Kitajima 1), H. Takahashi 2), K. Ishii 1), J. Sato 1), T. Ambo 1), M. Kanno 1), A. Okamoto 1), M. Sasao 1), S. Inagaki 3), M. Takayama

More information

FE FORMULATIONS FOR PLASTICITY

FE FORMULATIONS FOR PLASTICITY G These slides are designed based on the book: Finite Elements in Plasticity Theory and Practice, D.R.J. Owen and E. Hinton, 1970, Pineridge Press Ltd., Swansea, UK. 1 Course Content: A INTRODUCTION AND

More information