TSC Simulations of Alcator C-MOD Discharges IlIl: Study of Axisymmetric Stability
|
|
- Alison Norman
- 6 years ago
- Views:
Transcription
1 PFC/RR-9-9 DOE/ET TSC Simulations of Alcator C-MOD Discharges ll: Study of Axisymmetric Stability J.J. Ramos Plasma Fusion Center Massachusetts nstitute of Technology Cambridge, MA 2139 June 199 This work was supported by the U. S. Department of Energy Contract No. DE-AC2-78ET5113. Reproduction, translation, publication, use and disposal, in whole or in part by or for the United States government is permitted.
2 TSC Simulations of Alcator C.-MOD Discharges : Study of Axisymmetric Stability J. J. Ramos PLASMA FUSON CENTER, MT, Cambridge, MA 2139 Abstract The axisymmetric stability of the single X-point, nominal Alcator C-MOD configuration is investigated with the Tokamak Simulation Code. The resistive wall passive growth rate, in the absence of feedback stabilization, is obtained. The instability is suppressed with an appropriate active feedback system.
3 One of the most useful applications of the Tokamak Simulation Code (1] (TSC) is the analysis of the axisymmetric instability and its active feedback control for general plasma cross sections and current profiles. TSC models the time evolution of a twodimensional, axially symmetric plasma fluid and its electromagnetic interaction with the external field system, through a tokamak discharge. Therefore, it provides a complete, non linear description of the tokamak axisymmetric stability behavior. The dynamical equations solved by TSC are those of a full two-fluid transport model with appropriate phenomenological diffusion coefficients. Thus, this code is able to describe the plasma evolution in both the Alfvin and diffusive transport time scales. Since these time scales are separated by many orders of magnitude, economical time integration requires some numerical artifact. n TSC, this is accomplished by assuming an artificial ion mass equal to a factor fjee times the actual mass. Hence, the Alfvin speed is reduced by a factor ffe so that a practical integration time step that is still smaller than the shortest characteristic time scale can be adopted. n order to obtain realistic predictions, a convergence study towards the physical value ff., = 1 must be carried out. f no instabilities growing on the Alfvin time scale are present, an adequate description is obtained with as large ffee values (typically of the order of 1') as to make the Alfvin time comparable to the resistive diffusion time. This is the assumption made when modeling the evolution of a whole tokamak discharge, as done in Ref. 2 for the full 3 s duration of an Alcator C-MOD shot. However, to test the stability against axisymmetric modes that can grow in Alfvin-like time scales, a detailed convergence towards low ffpe values is necessary. Due to computer limitations, this can be carried out only over short real time intervals. n this work we chose to analyze the axisymmetric stability of the Alcator C-MOD 1
4 nominal configuration at the middle of the current flat-top, as generated by the TSC simulation described in Ref. 2, 1.5 s into the discharge. At this point, the plasma current equals 3 Mamp, the toroidal field at the plasma center is 9 T, the major and minor radii are R, =.665m, a =.21m, the separatrix elongation and triangularity are x. = 1.75, & =.4, and at the 95% relative to the separatrix flux surface n95 = 1.6, 95 =.3. The reader is referred to Ref. 2 for further details and definitions. A TSC run is restarted at this time with the correct currents in the active coils, but with the induced currents in the vacuum vessel suppressed. This results in an initial transient phase of unphysical eddy currents induced in the vacuum vessel that, since the plasma equilibrium is vertically asymmetric, are sufficient to trigger the vertical instability. The evolution of the latter is studied by following the plasma motion for the next 16 ms with low ffac values. This is repeated under two different scenarios. First, the instability passive growth rate is obtained by switching off the feedback control systems and letting the active coils carry only the preprogrammed currents. Second, the active control of the instability is investigated by switching the feedback systems on. Two independent observables are used to diagnose the plasma evolution: the vertical position of the magnetic axis and the poloidal magnetic flux difference between two observation loops located at R =.8 m, Z = ±.62 m. Figures 1 and 2 show their time derivatives as functions of time in semi-logarithmic plots, for the passive growth simulation without feedback. MKS units are used in all figures unless otherwise specified. The results displayed in Figs. 1 and 2 are obtained with ff.c = 15, but their characteristics are general. Three distinct phases can be identified: an initial transient phase is followed by a period of linear exponential growth after which the perturbation amplitude becomes too 2
5 large, the plasma evolution enters a non-linear regime and the equilibrium is rapidly lost. The evolution of the plasma boundary during this 16 ms simulation with ff.c = 15 is shown in Fig. 3. Figure 4 displays the corresponding induced currents in the vacuum vessel. The linear phase lasts for two exponential growth times approximately, which allows to establish a well defined linear growth rate. Such inverse linear growth rates are plotted in Fig. 5 as functions of ff.c. Circles and triangles correspond to the values obtained with the magnetic axis displacement and flux difference diagnostics, respectively. Two sets of points are shown in Fig. 5. They correspond to two values of yet another artificial parameter, a numerical viscosity introduced in TSC to ensure numerical stability, that should be extrapolated to zero. By extrapolating the data in Fig. 5 to ffac = 1, we obtain the physical passive growth time of about 1 ms. The characteristic L/R time constant of the vacuum vessel is considerably larger, about 16 ms. This rather fast instability growth rate reflects the fact that no close fitting conductor structure exists around the Alcator C-MOD plasma, and makes the problem of its active feedback control a challenging one. The feedback control system implemented in TSC is a two-level proportional-derivativeintegral (PD) scheme defined in the following way. Given a preprogrammed current P, (function of time) in a coil or linear combination of coils, the feedback current is defined by: da fb = P, +gpa+9d dt + 9 f Adt, (1) where A is the feedback signal and gp,gd,g are the gain coefficients. The difference between f b and the actual coil current at the time,,, is used to determine the incremental applied voltage which in our calculation is simply given by a proportional law: AV=gPV(fb-.c). (2) 3
6 Five independent such systems are used in our simulation. Their characteristics and gain coefficients are summarized in the following table. TABLE A gp gd i EP3 (A7P) X 15-4 x 12 QPU (AP) x 15 QPL (A3-1.5 x 1 5 NUL Aplama 5.2 X x 14 EFC AZazi X 13 Table : Definition of the active feedback systems. The gain coefficients are in MKS units. The first system acts on the vertical field coil EF3 and controls the radial position of the plasma. The second and third systems control the upper and lower elongation respectively and act on the linear combinations: QPU(L) = OH2U(L) -. 8 EF1U(L) + -1EF2 (3) that produce approximate quadrupole fields. The feedback signals for these first three systems are the flux differences between pairs of points that are expected to lie on the same magnetic surface and are moving in time. The fourth system controls the total plasma current and acts on the combination: NUL = OH (oH2U + OH2L) +.48 (EF1u + EF1L) +.21EF ief3 (4) that produces an approximate field null. ts signal is the difference between the actual and preprogrammed plasma current. The fifth system controls the vertical position of the 4
7 plasma and acts on the EFC coil. This coil has its upper and lower sections connected in anti-series to produce a radial magnetic field. ts signal is the difference between the actual and preprogrammed vertical position of the magnetic axis. The feedback signals used in our simulation are supposed to mimic the information gathered by the whole set of magnetic probe measurements in the actual experiment. The voltage gain coefficient gj, is set equal to.4 ohm for all systems. n addition, a maximum voltage cutoff of 2 V is set on each coil filament of our model, regardless of the demands of the feedback algorithm, in order to simulate realistic power supply and insulation constraints. The axisymmetric stability simulation is now repeated with these feedback systems in place. The resulting magnetic axis displacement and flux difference signals are shown in Figs. 6 and 7 as functions of time for the 16 ms simulation. Results are given for four values of the Alfven velocity slowing factor ff., down to ff~c = 25. n contrast with the passive simulation illustrated in Figs. 1-5, we can conclude now that the instability is suppressed by the active feedback even after we extrapolate to low ff.c. The evolution of the plasma boundary through this 16 ms simulation is shown in Fig. 8 for the case ff., = 15, to be compared with Fig. 3. The induced currents in the vacuum vessel are shown in Fig. 9, to be compared with Fig. 4. The currents and voltages in the active coils are given in Figs. 1-25, all of which show a stable behavior. We point out that the 2 V per filament limit on the vertical control coil EFC (16 V total for its four upper and four lower filaments) is sufficient to provide stability in our simulation. The EFC power supply in the actual Alcator C-MOD tokamak is rated at a maximum ±5 V. Finally we wish to call attention to the glitch observed around t = s in the ff., = 25 case. This is a spurious feature, presumably triggered by some numerical (finite 5
8 mesh size or truncation) inaccuracy, which is nonetheless successfully quenched by the feedback system. Such numerical problems set a practical limit as far as the convergence analysis with respect to ffac is concerned, because increasing the numerical accuracy and decreasing the computational grid spacing are unaffordable with our present day supercomputer capabilities. However, the results obtained with ff. > 25 provide sufficient basis for predicting a stable extrapolated behavior at the physical ffac = 1. Acknowledgements The author thanks S. Jardin for providing the TSC code and offering continuous assistance in its running. He also appreciates the useful discussions and help provided by the members of the Alcator group, especially S. Fairfax, R. Granetz, P. Hakkarainen, D. Humphreys,. Hutchinson and S. Wolfe. This work was supported by the U.S. Department of Energy under Contract No. DE-AC2-78ET
9 References [1] S.C. Jardin, N. Pomphrey and J. DeLucia, J. Computational Physics 66, 481 (1986). [2] J.J. Ramos, Massachusetts nstitute of Technology Report PFC/RR-9-2 (199). 7
10 Figure Captions [Fig. 1] Vertical displacement of the magnetic axis in the passive axisymmetric instability simulation with ff., = 15. [Fig. 2] Flux difference between observation points at R =.8 m, Z = t.62 m in the passive instability simulation with ffee = 15. [Fig. 3] Evolution of the plasma boundary in the 16 ms passive instability simulation with ff dc= 15. [Fig. 4] Vacuum vessel induced currents in the passive instability simulation with ffhc = 15. Each trace corresponds to one filament of our computational model. [Fig. 5] Linear growth times of the passive axisymmetric instability as functions of the Alfvin velocity slowing factor ffec. Circles and triangles are obtained with the magnetic axis displacement and flux difference diagnostics, respectively. The two sets of points correspond to two values of the numerical viscosity. [Fig. 6] Vertical displacement of the magnetic axis in the active feedback control simulations. [Fig. 7] Flux difference between observation points at R =.8 m, Z =.62 m in the active feedback control simulations. [Fig. 8] Evolution of the plasma boundary in the 16 ms active feedback control simulation with ff,, = 15. [Fig. 9] Vacuum vessel induced currents in the active feedback control simulations. [Fig. 1] Current in OH1 coil with the active feedback systems on. Magnitudes plotted correspond to one filament of our model. 8
11 spond to one filament of our model. [Fig. 11] Voltage in OH1 coil with the active feedback systems on. Each trace corresponds to one filament of our model. [Fig. 12] Current in OH2U coil with active feedback on. [Fig. 13] Voltage in OH2U coil with active feedback on. [Fig. 14] Current in OH2L coil with active feedback on. [Fig. 15] Voltage in OH2L coil with active feedback on. [Fig. 16] Current in EF1U coil with active feedback on. [Fig. 17] Voltage in EF1U coil with active feedback on. [Fig. 18] Current in EFL coil with active feedback on. [Fig. 19] Voltage in EF1L coil with active feedback on. [Fig. 2] Current in EF2 coil with active feedback on. [Fig. 21] Voltage in EF2 coil with active feedback on. [Fig. 22] Current in EF3 coil with active feedback on. [Fig. 23] Voltage in EF3 coil with active feedback on. [Fig. 24] Current in EFC coil with active feedback on. [Fig. 25] Voltage in EFC coil with active feedback on. 9
12 12 daz -i / 'p 'p 'p 'p 1 TR L NL p* 1 1~ Figure 1 1
13 1 daqi d t 1- TR L NL Figure 2 11
14 .7.6.4D.3Z l -. 2~ -3. o C C n ' Figre 12
15 1 C:) -1 LnUl) Ul) U-) )U L Figure 4 13
16 .3 Y< A 2 x v.2 A A A A SW ff a c Figure 5 14
17 daz dt 1-1 ffac= 25 1C t Figure 6 15
18 1~ d A q d t fac=25 o t Figure 7 16
19 7 T L.L-L L 1. LLL c, LM EM P99M CKDOM DQXDOM Domm DZKDM DONN D D CN -~ * ~~ C" CD C. U, ~O Figure 8 17
20 c:.1 e.> ~ r. TME(SEC) ffac = fac = 1 C Q= ifme (SEC) f ac 5 o o c ~ ME (SEC) 2 ffac =25 a- o cc C a TME(SEC) Figure 9 18
21 ffac = 15 Q S -6 o -J fl * is o e a a a , 4, 4, 4, 4, 4, ifl 4~ 4, UTU ME( SEC) i ffac = h o -. -~ o a a a a 4S ~ 4~ C 4, SE( SC) S t a -- ~ - - tl (SEC) '-.~ - * C r4 o a a , C 4,.. 4, 4, 4, ffac = ffac = 2 CD, -6 Figure 1 19
22 . _ i - i 1.1 i E U o -. 2 TM( - C) - S = C*4 * E ffac = J-.1 -, o * - -_- o r~. to ~ o r. - to o o o a, a, a, a, a, a, a~ a~ a, ffac = ac = o -. 2 T ur(~rr~ ri-s,-s o a a, a, Sn tc~ U~ a, a, a, a, ! fac = ol. S-.2 TME(SEC) go.- - Figure 11 2
23 CL -1-2 ffac = 15 T ME(SEC f ac = 1-2 _ 1&. ME( SEC) a - -, ) : U -~- -Sffac = 5 - _-~ -b- --- o (N - C C (N - o ~1.,ME ( SEC) -1 a -t ffac = e -3 a ~ ~ ~ ~ C lo,- *4 4 ( TN(SEC) Figure 12 21
24 ffac = cc. (SEC) f ffac = 1-2 _ Mr(SEC) ~ / (.ini - 1 ffac = 5 * o - ri C a a N f VE(SEC). 1 7, ffac = 25 CL S -.2 nut (sec) us~w us U Us us in - 4 Figure 13 22
25 ff ac = 15 t -5 T U~ ~fi~ Z W7L- S -2-3 ffac = 1 CD * - * - o ~ ~~ e C - E * OEC ffac = ed ' C C d * T ime(sec) ffac = 25 a o ~ C C C.~ C C o ai fl ~.4,.4,.4, C TME(SEC) Figure 14 23
26 ff ac = 15 cc -.15 o -. 2 m ((SEC). ff ac = o 'N - t C e.- rim E(SCC) ffac = TM (SEC) ffac = j.o o t in t o o t t ot s e Figure 15 24
27 1 ~w ~- 4 ffac = 15 2 C ' C o ' ' ' '. ' '. ' ME(SEC) a- -' 6 4 D 2 ffac = 1 C ME (SEC) Z;?.. ' 1 at 8 6 f fac = 5 4 o L ~ 'N - 4 C (.4 ~ O '. ' '.. ' ' ME (SEC) w f ac = 25 a- 4 2 A - 7 o o a a a e..d~. ' ME(SEC) a ~ 4 T Figure 16 25
28 > -. 1 ffac = o-.2 TME(SEC) = e~. -. C = C C'. - t~ = a u~ fl 1 to U) C ffac = 1-1 o -. 2 '- - 4 lmt( EC).1-9- ffac = ' - C cc C C C C ME(SEC).1 AVh,. fc = CL TN(( sec) Figure 17 26
29 2 15 a- 1 o C 44 * 5 ME( SEC) ff ac = 15 o o o ~ -v - -w- -~ 2 ffac = 1 x C. 15 T W SEC) * 4 2 x 1 5 e 1 ffac =5. ME(SEC) ac = T C o a - 4,, 44 j 4, 4 4 MC(SEC) Figure 18 27
30 .5 ' U-> ffac = 15 o m-- ME(SEC) ff ac = 'i-l _E ' ).1 1 ffac = 5 a r~. a - a a r - ( ME(SEC) - 1 o a U, U U~ ( U ~ U~ ( ffac = S-.2 2 ȧ a a3 a ('4. w U, U, U MC(SEC) Figure 19 28
31 12 1 ~3 =~w =~= =~ =1 S 8 4 ffac = 15 CD 2 A -- C 1 M(SEC) '2 1 U -~ - -~ ~- -~ -4 S ffac = 1 (c2 - -L -- TlMO(SC) ~ 9- -~ ~ -U- S 8 6 ffac = 5 CL 4 at 2 A~ o -. - ~ ME(SEC), ffac = 25 8e CD 2 L o (N.4" (N t C (i.fl... ~... itiwc(sec) Figure 2 29
32 o -. 1 ffac = 15 o TME(SEC) - a r f ac =1 c C -. 5 o r- ( -. = C~. P ME( SEC) f r w/ia l- ffac = o ME( SEC) = o -. 2 C= a C. - 4 q 4 Figure 21 3
33 m ff ac = 15-4 S o 'N '4- ' ' * T M((S(C) ff ac = _ ~= -'= -- - _ 'ME(SEC) o z - m ffac = 5. S -4 <3-5 _ a, a, a a, a,, a, a, a - -~ -o T t ME (SEC) S ~ ffac = 25 (3-5 C ('4 '4- ' *" *~ - o ~ U, U, 4~ ' ' ime(sec) Figure 22 31
34 ffac = 15 o -. 2 o - to ~ C tn ~ to C C C ~. n n 1 to U, to MC(S[C) 5 ] ffac = M ,= - 2 At C C M (str A ffac = 5 _2 M SEC) fac = ~ ME(SEC) Figure 23 32
35 fac = 15 CD, ME(SEC) --- N T ~ ffac = 1 a. NE(SEC) o o+ - d * 1 T ffac = 5 1. x.5 o a a E (SEC) -5 CD, 4) 4) 4).5 4) ) 4)All4 fac = MF 1-T Ftr 1 ~F a ox CW 1!N Figure 24 33
36 ~ - fac = QD d t = C~~ C C tt tt g~ ME(SEC) 2 1T ~- -4- ~ ffac = o N. * C = C (N - i o o o C C ft C U- Cl n tt n tt t T dm(sec) Q~ -4- ffc = 5 o -. 2 H U - f (WE (SEC).2 - o m -.1. ffac = 25 an o Figure 25 34
The Effects of Noise and Time Delay on RWM Feedback System Performance
The Effects of Noise and Time Delay on RWM Feedback System Performance O. Katsuro-Hopkins, J. Bialek, G. Navratil (Department of Applied Physics and Applied Mathematics, Columbia University, New York,
More informationRole 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 informationEffects of Noise in Time Dependent RWM Feedback Simulations
Effects of Noise in Time Dependent RWM Feedback Simulations O. Katsuro-Hopkins, J. Bialek, G. Navratil (Department of Applied Physics and Applied Mathematics, Columbia University, New York, NY USA) Building
More informationWave 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 informationPlasma 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 informationRequirements for Active Resistive Wall Mode (RWM) Feedback Control
Requirements for Active Resistive Wall Mode (RWM) Feedback Control Yongkyoon In 1 In collaboration with M.S. Chu 2, G.L. Jackson 2, J.S. Kim 1, R.J. La Haye 2, Y.Q. Liu 3, L. Marrelli 4, M. Okabayashi
More informationDesign 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 informationMagnetohydrodynamic stability of negative central magnetic shear, high pressure ( pol 1) toroidal equilibria
Magnetohydrodynamic stability of negative central magnetic shear, high pressure ( pol 1) toroidal equilibria Robert G. Kleva Institute for Plasma Research, University of Maryland, College Park, Maryland
More informationRESISTIVE WALL MODE STABILIZATION RESEARCH ON DIII D STATUS AND RECENT RESULTS
RESISTIVE WALL MODE STABILIZATION RESEARCH ON STATUS AND RECENT RESULTS by A.M. Garofalo1 in collaboration with J. Bialek,1 M.S. Chance,2 M.S. Chu,3 T.H. Jensen,3 L.C. Johnson,2 R.J. La Haye,3 G.A. Navratil,1
More informationDesign calculations for fast plasma position control in Korea Superconducting Tokamak Advanced Research
Fusion Engineering and Design 45 (1999) 101 115 Design calculations for fast plasma position control in Korea Superconducting Tokamak Advanced Research Hogun Jhang a, *, C. Kessel b, N. Pomphrey b, S.C.
More informationExperimental Investigations of Magnetic Reconnection. J Egedal. MIT, PSFC, Cambridge, MA
Experimental Investigations of Magnetic Reconnection J Egedal MIT, PSFC, Cambridge, MA Coronal Mass Ejections Movie from NASA s Solar Dynamics Observatory (SDO) Space Weather The Solar Wind affects the
More informationELECTROMAGNETIC LIQUID METAL WALL PHENOMENA
ELECTROMAGNETIC LIQUID METAL WALL PHENOMENA BY BOB WOOLLEY 15-19 FEBRUARY 1999 APEX-6 MEETING LIQUID WALLS A sufficiently thick, flowing, liquid first wall and tritium breeding blanket which almost completely
More informationCurrent Drive Experiments in the HIT-II Spherical Tokamak
Current Drive Experiments in the HIT-II Spherical Tokamak T. R. Jarboe, P. Gu, V. A. Izzo, P. E. Jewell, K. J. McCollam, B. A. Nelson, R. Raman, A. J. Redd, P. E. Sieck, and R. J. Smith, Aerospace & Energetics
More informationSawteeth in Tokamaks and their relation to other Two-Fluid Reconnection Phenomena
Sawteeth in Tokamaks and their relation to other Two-Fluid Reconnection Phenomena S. C. Jardin 1, N. Ferraro 2, J. Chen 1, et al 1 Princeton Plasma Physics Laboratory 2 General Atomics Supported by the
More informationMassachusetts Institute of Technology 22.68J/2.64J Superconducting Magnets. February 27, Lecture #4 Magnetic Forces and Stresses
Massachusetts Institute of Technology.68J/.64J Superconducting Magnets February 7, 003 Lecture #4 Magnetic Forces and Stresses 1 Forces For a solenoid, energy stored in the magnetic field acts equivalent
More informationModel based estimation of the Eddy currents for the ITER tokamak *
Model based estimation of the Eddy currents for the ITER tokamak * Alfredo Pironti 1 Consorzio CREATE - University of Naples Federico II Via Claudio 21, 80125 Napoli, Italy E-mail: pironti@unina.it Roberto
More informationPlasma Shape Feedback Control on EAST
1 EXC/P2-09 Plasma Shape Feedback Control on EAST Q.P. Yuan 1), B.J. Xiao 1), Z.P. Luo 1), M.L. Walker 2), A.S. Welander 2), A. Hyatt 2), J.P. Qian 1), D.A. Humphreys 2), J.A. Leuer 2), R.D. Johnson 2),
More informationA Study of Directly Launched Ion Bernstein Waves in a Tokamak
PFC-/JA-86-6 A Study of Directly Launched Ion Bernstein Waves in a Tokamak Y. Takase, J. D. Moody, C. L. Fiore, F. S. McDermott, M. Porkolab, and J. Squire Plasma Fusion Center Massachusetts Institute
More informationNon-Solenoidal Plasma Startup in
Non-Solenoidal Plasma Startup in the A.C. Sontag for the Pegasus Research Team A.C. Sontag, 5th APS-DPP, Nov. 2, 28 1 Point-Source DC Helicity Injection Provides Viable Non-Solenoidal Startup Technique
More informationPlasma Fusion Center Massachusetts Institute of Technology Cambridge, MA Burrell, K.H. General Atomics PO Box San Diego, CA
PFC/JA-95-28 Edge Turbulence Measurements during the L- to H-Mode Transition by Phase Contrast Imaging on DIII-Dt Coda, S.; Porkolab, M.; Plasma Fusion Center Massachusetts Institute of Technology Cambridge,
More informationPredictive Simulation of Global Instabilities in Tokamaks
Predictive Simulation of Global Instabilities in Tokamaks Stephen C. Jardin Princeton Plasma Physics Laboratory Fourth ITER International Summer School IISS 2010 Institute of Fusion Studies University
More informationModel based optimization and estimation of the field map during the breakdown phase in the ITER tokamak
Model based optimization and estimation of the field map during the breakdown phase in the ITER tokamak Roberto Ambrosino 1 Gianmaria De Tommasi 2 Massimiliano Mattei 3 Alfredo Pironti 2 1 CREATE, Università
More informationGA A22684 CONTROL OF PLASMA POLOIDAL SHAPE AND POSITION IN THE DIII D TOKAMAK
GA A22684 CONTROL OF PLASMA POLOIDAL SHAPE AND POSITION IN THE DIII D TOKAMAK by M.L. WALKER, D.A. HUMPHREYS, and J.R. FERRON NOVEMBER 1997 DISCLAIMER This report was prepared as an account of work sponsored
More informationELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations
1 EXC/P5-02 ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations B. Hudson 1, T.E. Evans 2, T.H. Osborne 2, C.C. Petty 2, and P.B. Snyder 2 1 Oak Ridge Institute for Science
More information- 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 informationDynamical plasma response of resistive wall modes to changing external magnetic perturbations
Dynamical plasma response of resistive wall modes to changing external magnetic perturbations M. Shilov, C. Cates, R. James, A. Klein, O. Katsuro-Hopkins, Y. Liu, M. E. Mauel, D. A. Maurer, G. A. Navratil,
More informationDerivation of dynamo current drive in a closed current volume and stable current sustainment in the HIT SI experiment
Derivation of dynamo current drive and stable current sustainment in the HIT SI experiment 1 Derivation of dynamo current drive in a closed current volume and stable current sustainment in the HIT SI experiment
More informationDIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH
DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH by K.H. Burrell Presented at High Temperature Plasma Diagnostics 2 Conference Tucson, Arizona June 19 22, 2 134 /KHB/wj ROLE OF DIAGNOSTICS IN ADVANCED TOKAMAK
More informationCharacterization 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 informationSTABILIZATION 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 informationExtended Lumped Parameter Model of Resistive Wall Mode and The Effective Self-Inductance
Extended Lumped Parameter Model of Resistive Wall Mode and The Effective Self-Inductance M.Okabayashi, M. Chance, M. Chu* and R. Hatcher A. Garofalo**, R. La Haye*, H. Remeirdes**, T. Scoville*, and T.
More informationFull-wave Simulations of Lower Hybrid Wave Propagation in the EAST Tokamak
Full-wave Simulations of Lower Hybrid Wave Propagation in the EAST Tokamak P. T. BONOLI, J. P. LEE, S. SHIRAIWA, J. C. WRIGHT, MIT-PSFC, B. DING, C. YANG, CAS-IPP, Hefei 57 th Annual Meeting of the APS
More informationDirect drive by cyclotron heating can explain spontaneous rotation in tokamaks
Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks J. W. Van Dam and L.-J. Zheng Institute for Fusion Studies University of Texas at Austin 12th US-EU Transport Task Force Annual
More informationFormation 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 informationTSC 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 informationICRF Minority-Heated Fast-Ion Distributions on the Alcator C-Mod: Experiment and Simulation
ICRF Minority-Heated Fast-Ion Distributions on the Alcator C-Mod: Experiment and Simulation A. Bader 1, P. Bonoli 1, R. Granetz 1, R.W. Harvey 2, E.F. Jaeger 3, R. Parker 1, S. Wukitch 1. 1)MIT-PSFC, Cambridge,
More informationDynamical plasma response of resistive wall modes to changing external magnetic perturbations a
PHYSICS OF PLASMAS VOLUME 11, NUMBER 5 MAY 2004 Dynamical plasma response of resistive wall modes to changing external magnetic perturbations a M. Shilov, b) C. Cates, R. James, A. Klein, O. Katsuro-Hopkins,
More informationResistive Wall Mode Observation and Control in ITER-Relevant Plasmas
Resistive Wall Mode Observation and Control in ITER-Relevant Plasmas J. P. Levesque April 12, 2011 1 Outline Basic Resistive Wall Mode (RWM) model RWM stability, neglecting kinetic effects Sufficient for
More informationThe compact dipole configuration for plasma confinement
The compact dipole configuration for plasma confinement D. A. Baver Lodestar Research Corporation, Boulder, Colorado, 80301 March, 2011 Submitted to Journal of Fusion Energy LRC-11-141 Lodestar Research
More informationThe Neutron Diagnostic Experiment for Alcator C-Mod
PFC/JA-9-16 The Neutron Diagnostic Experiment for Alcator C-Mod C. L. Fiore, R. S. Granetz Plasma Fusion Center Massachusetts Institute of Technology -Cambridge, MA 2139 May, 199 To be published in Review
More informationExperimental Vertical Stability Studies for ITER Performance and Design Guidance
1 IT/2-4Rb Experimental Vertical Stability Studies for ITER Performance and Design Guidance D.A. Humphreys 1), T.A. Casper 2), N. Eidietis 1), M. Ferrara 3), D.A. Gates 4), I.H. Hutchinson 3), G.L. Jackson
More informationPedestal Stability and Transport on the Alcator C-Mod Tokamak: Experiments in Support of Developing Predictive Capability
1 EX/P4-15 Pedestal Stability and Transport on the Alcator C-Mod Tokamak: Experiments in Support of Developing Predictive Capability J.W. Hughes 1, P.B. Snyder 2, X. Xu 3, J.R. Walk 1, E.M. Davis 1, R.M.
More informationPlasma Current, Position and Shape Control June 2, 2010
, Position and Shape Control June 2, 2010 June 2, 2010 - ITER International Summer School 2010 Control 1 in collaboration with CREATE and EFDA-JET PPCC contributors 1 CREATE, Università di Napoli Federico
More informationToroidal flow stablization of disruptive high tokamaks
PHYSICS OF PLASMAS VOLUME 9, NUMBER 6 JUNE 2002 Robert G. Kleva and Parvez N. Guzdar Institute for Plasma Research, University of Maryland, College Park, Maryland 20742-3511 Received 4 February 2002; accepted
More informationStabilization of sawteeth in tokamaks with toroidal flows
PHYSICS OF PLASMAS VOLUME 9, NUMBER 7 JULY 2002 Stabilization of sawteeth in tokamaks with toroidal flows Robert G. Kleva and Parvez N. Guzdar Institute for Plasma Research, University of Maryland, College
More information1 EX/P7-12. Transient and Intermittent Magnetic Reconnection in TS-3 / UTST Merging Startup Experiments
1 EX/P7-12 Transient and Intermittent Magnetic Reconnection in TS-3 / UTST Merging Startup Experiments Y. Ono 1), R. Imazawa 1), H. Imanaka 1), T. Hayamizu 1), M. Inomoto 1), M. Sato 1), E. Kawamori 1),
More informationPREDICTIVE 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 informationHighlights from (3D) Modeling of Tokamak Disruptions
Highlights from (3D) Modeling of Tokamak Disruptions Presented by V.A. Izzo With major contributions from S.E. Kruger, H.R. Strauss, R. Paccagnella, MHD Control Workshop 2010 Madison, WI ..onset of rapidly
More informationObservations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas
1 EX/P5-4 Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas J.E. Rice 1), A.C. Ince-Cushman 1), P.T. Bonoli 1), M.J. Greenwald 1), J.W. Hughes 1), R.R. Parker 1), M.L. Reinke
More informationDouble 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 informationStudy of B +1, B +4 and B +5 impurity poloidal rotation in Alcator C-Mod plasmas for 0.75 ρ 1.0.
Study of B +1, B +4 and B +5 impurity poloidal rotation in Alcator C-Mod plasmas for 0.75 ρ 1.0. Igor Bespamyatnov, William Rowan, Ronald Bravenec, and Kenneth Gentle The University of Texas at Austin,
More informationRWM Control in FIRE and ITER
RWM Control in FIRE and ITER Gerald A. Navratil with Jim Bialek, Allen Boozer & Oksana Katsuro-Hopkins MHD Mode Control Workshop University of Texas-Austin 3-5 November, 2003 OUTLINE REVIEW OF VALEN MODEL
More informationFlow and dynamo measurements in the HIST double pulsing CHI experiment
Innovative Confinement Concepts (ICC) & US-Japan Compact Torus (CT) Plasma Workshop August 16-19, 211, Seattle, Washington HIST Flow and dynamo measurements in the HIST double pulsing CHI experiment M.
More informationThe Field-Reversed Configuration (FRC) is a high-beta compact toroidal in which the external field is reversed on axis by azimuthal plasma The FRC is
and Stability of Field-Reversed Equilibrium with Toroidal Field Configurations Atomics General Box 85608, San Diego, California 92186-5608 P.O. APS Annual APS Meeting of the Division of Plasma Physics
More informationSTABILIZATION OF THE RESISTIVE WALL MODE IN DIII D BY PLASMA ROTATION AND MAGNETIC FEEDBACK
GA A24014 STABILIZATION OF THE RESISTIVE WALL MODE IN DIII D BY PLASMA ROTATION AND MAGNETIC FEEDBACK by M. Okabayashi, J. Bialek, M.S. Chance, M.S. Chu, E.D. Fredrickson, A.M. Garofalo, R. Hatcher, T.H.
More informationNIMROD FROM THE CUSTOMER S PERSPECTIVE MING CHU. General Atomics. Nimrod Project Review Meeting July 21 22, 1997
NIMROD FROM THE CUSTOMER S PERSPECTIVE MING CHU General Atomics Nimrod Project Review Meeting July 21 22, 1997 Work supported by the U.S. Department of Energy under Grant DE-FG03-95ER54309 and Contract
More informationOscillating-Field Current-Drive Experiment on MST
Oscillating-Field Current-Drive Experiment on MST K. J. McCollam, J. K. Anderson, D. J. Den Hartog, F. Ebrahimi, J. A. Reusch, J. S. Sarff, H. D. Stephens, D. R. Stone University of Wisconsin-Madison D.
More informationNon-linear MHD Simulations of Edge Localized Modes in ASDEX Upgrade. Matthias Hölzl, Isabel Krebs, Karl Lackner, Sibylle Günter
Non-linear MHD Simulations of Edge Localized Modes in ASDEX Upgrade Matthias Hölzl, Isabel Krebs, Karl Lackner, Sibylle Günter Matthias Hölzl Nonlinear ELM Simulations DPG Spring Meeting, Jena, 02/2013
More informationVertical Displacement Events in Shaped Tokamaks. Abstract
Vertical Displacement Events in Shaped Tokamaks A. Y. Aydemir Institute for Fusion Studies The University of Texas at Austin Austin, Texas 78712 USA Abstract Computational studies of vertical displacement
More informationAnalytical Study of RWM Feedback Stabilisation with Application to ITER
CT/P- Analytical Study of RWM Feedback Stabilisation with Application to ITER Y Gribov ), VD Pustovitov ) ) ITER International Team, ITER Naka Joint Work Site, Japan ) Nuclear Fusion Institute, Russian
More informationThe FTU facilities. Regarding the the control and data acquisition system, last year we carried out the following activities:
The FTU facilities FTU Machine Summary of the machine operation During 2005, the machine operated at the high level of 91% of successful pulses. The experimental activity started in March and went on till
More informationComparison of Divertor Heat Flux Splitting by 3D Fields with Field Line Tracing Simulation in KSTAR
1 Comparison of Divertor Heat Flux Splitting by 3D Fields with Field Line Tracing Simulation in KSTAR W. Choe 1,2*, K. Kim 1,2, J.-W. Ahn 3, H.H. Lee 4, C.S. Kang 4, J.-K. Park 5, Y. In 4, J.G. Kwak 4,
More informationKSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta
1 THS/P2-05 KSTAR Equilibrium Operating Space and Projected Stabilization at High Normalized Beta Y.S. Park 1), S.A. Sabbagh 1), J.W. Berkery 1), J.M. Bialek 1), Y.M. Jeon 2), S.H. Hahn 2), N. Eidietis
More informationEffect of non-axisymmetric magnetic perturbations on divertor heat and particle flux profiles
1 EXD/P3-01 Effect of non-axisymmetric magnetic perturbations on divertor heat and particle flux profiles J-W. Ahn 1, J.M. Canik 1, R. Maingi 1, T.K. Gray 1, J.D. Lore 1, A.G. McLean 1, J.-K. Park 2, A.L.
More informationHeat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment.
Heat Flux Management via Advanced Magnetic Divertor Configurations and Divertor Detachment E. Kolemen a, S.L. Allen b, B.D. Bray c, M.E. Fenstermacher b, D.A. Humphreys c, A.W. Hyatt c, C.J. Lasnier b,
More informationITER DIAGNOSTIC PORT PLUG DESIGN. N H Balshaw, Y Krivchenkov, G Phillips, S Davis, R Pampin-Garcia
N H Balshaw, Y Krivchenkov, G Phillips, S Davis, R Pampin-Garcia UKAEA, Culham Science Centre, Abingdon, Oxon,OX14 3DB, UK, nick.balshaw@jet.uk Many of the ITER diagnostic systems will be mounted in the
More informationNon-inductive plasma startup and current profile modification in Pegasus spherical torus discharges
Non-inductive plasma startup and current profile modification in Pegasus spherical torus discharges Aaron J. Redd for the Pegasus Team 2008 Innovative Confinement Concepts Workshop Reno, Nevada June 24-27,
More informationLower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation
Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation P.T. Bonoli, A. E. Hubbard, J. Ko, R. Parker, A.E. Schmidt, G. Wallace, J. C. Wright, and the Alcator C-Mod
More informationFilament-Circuit Model Analysis of Alcator C-MOD Vertical Stability
PFC/JA-89-28 Filament-Circuit Model Analysis of Alcator C-MOD Vertical Stability D. A. Humphreys and I. H. Hutchinson Plasma Fusion Center Massachusetts Institute of Technology Cambridge, MA 02139 June,
More informationObservation of Neo-Classical Ion Pinch in the Electric Tokamak*
1 EX/P6-29 Observation of Neo-Classical Ion Pinch in the Electric Tokamak* R. J. Taylor, T. A. Carter, J.-L. Gauvreau, P.-A. Gourdain, A. Grossman, D. J. LaFonteese, D. C. Pace, L. W. Schmitz, A. E. White,
More informationAnalysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission
Analysis and modelling of MHD instabilities in DIII-D plasmas for the ITER mission by F. Turco 1 with J.M. Hanson 1, A.D. Turnbull 2, G.A. Navratil 1, C. Paz-Soldan 2, F. Carpanese 3, C.C. Petty 2, T.C.
More informationPossibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets
PFC/JA-91-5 Possibilities for Long Pulse Ignited Tokamak Experiments Using Resistive Magnets E. A. Chaniotakis L. Bromberg D. R. Cohn April 25, 1991 Plasma Fusion Center Massachusetts Institute of Technology
More informationJ. Kesner. April Plasma Fusion Center Massachusetts Institute of Technology Cambridge, Massachusetts USA
PFC/JA-88-38 Effect of Local Shear on Drift Fluctuation Driven T'ransport in Tokamaks J. Kesner April 1989 Plasma Fusion Center Massachusetts Institute of Technology Cambridge, Massachusetts 2139 USA Submitted
More informationBehavior of Compact Toroid Injected into the External Magnetic Field
Behavior of Compact Toroid Injected into the External Magnetic Field M. Nagata 1), N. Fukumoto 1), H. Ogawa 2), T. Ogawa 2), K. Uehara 2), H. Niimi 3), T. Shibata 2), Y. Suzuki 4), Y. Miura 2), N. Kayukawa
More informationarxiv: v1 [physics.plasm-ph] 11 Mar 2016
1 Effect of magnetic perturbations on the 3D MHD self-organization of shaped tokamak plasmas arxiv:1603.03572v1 [physics.plasm-ph] 11 Mar 2016 D. Bonfiglio 1, S. Cappello 1, M. Veranda 1, L. Chacón 2 and
More informationA method for calculating active feedback system to provide vertical position control of plasma in a tokamak
PRAMANA c Indian Academy of Sciences Vol. 68, No. 4 journal of April 2007 physics pp. 591 602 A method for calculating active feedback system to provide vertical position control of plasma in a tokamak
More informationHigh Beta Discharges with Hydrogen Storage Electrode Biasing in the Tohoku University Heliac
J. Plasma Fusion Res. SERIES, Vol. 8 (2009) High Beta Discharges with Hydrogen Storage Electrode Biasing in the Tohoku University Heliac Hiroyasu UTOH, Kiyohiko NISHIMURA 1), Hajime UMETSU, Keiichi ISHII,
More informationPlasma shielding during ITER disruptions
Plasma shielding during ITER disruptions Sergey Pestchanyi and Richard Pitts 1 Integrated tokamak code TOKES is a workshop with various tools objects Radiation bremsstrahlung recombination s line s cyclotron
More informationGA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME
GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME by R. NAZIKIAN, M.E. AUSTIN, R.V. BUDNY, M.S. CHU, W.W. HEIDBRINK, M.A. MAKOWSKI, C.C. PETTY, P.A. POLITZER, W.M. SOLOMON, M.A.
More informationResearch 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 informationComparing DINA code simulations with TCV experimental plasma equilibrium responses
1 Comparing DINA code simulations with TCV experimental plasma equilibrium responses R.R. Khayrutdinov 2, J.B. Lister 1, V.E. Lukash 3, J.P. Wainwright 4 1 Centre de Recherches en Physique des Plasmas,
More informationResistive 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 informationION THERMAL CONDUCTIVITY IN TORSATRONS. R. E. Potok, P. A. Politzer, and L. M. Lidsky. April 1980 PFC/JA-80-10
ION THERMAL CONDUCTIVITY IN TORSATRONS R. E. Potok, P. A. Politzer, and L. M. Lidsky April 1980 PFC/JA-80-10 ION THERMAL CONDUCTIVITY IN TORSATRONS R.E. Potok, P.A. Politzer, and L.M. Lidsky Plasma Fusion
More informationConnections between Particle Transport and Turbulence Structures in the Edge and SOL of Alcator C-Mod
Connections between Particle Transport and Turbulence Structures in the Edge and SOL of Alcator C-Mod I. Cziegler J.L. Terry, B. LaBombard, J.W. Hughes MIT - Plasma Science and Fusion Center th 19 Plasma
More informationDOPPLER RESONANCE EFFECT ON ROTATIONAL DRIVE BY ION CYCLOTRON MINORITY HEATING
DOPPLER RESONANCE EFFECT ON ROTATIONAL DRIVE BY ION CYCLOTRON MINORITY HEATING V.S. Chan, S.C. Chiu, Y.A. Omelchenko General Atomics, San Diego, CA, U.S.A. 43rd Annual APS Division of Plasma Physics Meeting
More informationA SUPERCONDUCTING TOKAMAK FUSION TRANSMUTATION OF WASTE REACTOR
A SUPERCONDUCTING TOKAMAK FUSION TRANSMUTATION OF WASTE REACTOR A.N. Mauer, W.M. Stacey, J. Mandrekas and E.A. Hoffman Fusion Research Center Georgia Institute of Technology Atlanta, GA 30332 1. INTRODUCTION
More informationParticle transport results from collisionality scans and perturbative experiments on DIII-D
1 EX/P3-26 Particle transport results from collisionality scans and perturbative experiments on DIII-D E.J. Doyle 1), L. Zeng 1), G.M. Staebler 2), T.E. Evans 2), T.C. Luce 2), G.R. McKee 3), S. Mordijck
More informationProgress Toward High Performance Steady-State Operation in DIII D
Progress Toward High Performance Steady-State Operation in DIII D by C.M. Greenfield 1 for M. Murakami, 2 A.M. Garofalo, 3 J.R. Ferron, 1 T.C. Luce, 1 M.R. Wade, 1 E.J. Doyle, 4 T.A. Casper, 5 R.J. Jayakumar,
More informationConfiguration Optimization of a Planar-Axis Stellarator with a Reduced Shafranov Shift )
Configuration Optimization of a Planar-Axis Stellarator with a Reduced Shafranov Shift ) Shoichi OKAMURA 1,2) 1) National Institute for Fusion Science, Toki 509-5292, Japan 2) Department of Fusion Science,
More informationGA A22443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D
GA A443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D by R.J. GROEBNER, T.N. CARLSTROM, K.H. BURRELL, S. CODA, E.J. DOYLE, P. GOHIL, K.W. KIM, Q. PENG, R. MAINGI, R.A. MOYER, C.L. RETTIG, T.L. RHODES,
More informationUpper Hybrid Resonance Backscattering Enhanced Doppler Effect and Plasma Rotation Diagnostics at FT-2 Tokamak
Upper Hybrid Resonance Backscattering Enhanced Doppler Effect and Plasma Rotation Diagnostics at FT- Tokamak A.B. Altukhov ), V.V. Bulanin ), V.V. Dyachenko ), L.A. Esipov ), M.V. Gorokhov ), A.D. Gurchenko
More informationGA A27857 IMPACT OF PLASMA RESPONSE ON RMP ELM SUPPRESSION IN DIII-D
GA A27857 IMPACT OF PLASMA RESPONSE ON RMP ELM SUPPRESSION IN DIII-D by A. WINGEN, N.M. FERRARO, M.W. SHAFER, E.A. UNTERBERG, T.E. EVANS, D.L. HILLIS, and P.B. SNYDER JULY 2014 DISCLAIMER This report was
More informationEquilibrium reconstruction improvement via Kalman-filter-based vessel current estimation at DIII-D
Fusion Engineering and Design 82 (2007) 1144 1152 Equilibrium reconstruction improvement via Kalman-filter-based vessel current estimation at DIII-D Y. Ou a, M.L. Walker b, E. Schuster a,, J.R. Ferron
More informationOptimization of Plasma Initiation Scenarios in JT-60SA
J. Plasma Fusion Res. SERIES, Vol. 9 (2010) Optimization of Plasma Initiation Scenarios in JT-60SA Makoto MATSUKAWA 1, Tsunehisa TERAKADO 1, Kunihito YAMAUCHI 1, Katsuhiro SHIMADA 1, Philippe CARA 2, Elena
More informationTH/P4-9. T. Takizuka 1), K. Shimizu 1), N. Hayashi 1), M. Hosokawa 2), M. Yagi 3)
1 Two-dimensional Full Particle Simulation of the Flow Patterns in the Scrape-off-layer Plasma for Upper- and Lower- Null Point Divertor Configurations in Tokamaks T. Takizuka 1), K. Shimizu 1), N. Hayashi
More informationDisruption mitigation in ITER
Disruption mitigation in ITER S.Putvinski, R.Pitts, M.Sugihara, L.Zakharov Page 1 Outline Introduction Massive gas injection for mitigation of thermal loads Forces on VV and in vessel components Suppression
More information*Visiting Scientist, on leave of absence from the Institute of Mechanics, Chinese Academy of Sciences, Beijing, China
A Combined Scheme of Adiabatic Compression and Accelerated Merging of Tokamak Tori Ming-Lun Xue* Plasma Fusion Center Massachusetts Institute of Technology Cambridge, MA 02139 PFC/RR-81-28 July 1981 *Visiting
More informationReal Plasma with n, T ~ p Equilibrium: p = j B
Real Plasma with n, T ~ p Equilibrium: p = j B B lines must lie in isobaric surfaces. Since B = 0, only possible if isobaric surfaces are topological tori. Magnetic field lines must form nested tori. Equilibrium
More informationElectrode and Limiter Biasing Experiments on the Tokamak ISTTOK
Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK C. Silva, H. Figueiredo, J.A.C. Cabral,, I. Nedzelsky, C.A.F. Varandas Associação Euratom/IST, Centro de Fusão Nuclear, Instituto Superior
More informationA Simulation Model for Drift Resistive Ballooning Turbulence Examining the Influence of Self-consistent Zonal Flows *
A Simulation Model for Drift Resistive Ballooning Turbulence Examining the Influence of Self-consistent Zonal Flows * Bruce I. Cohen, Maxim V. Umansky, Ilon Joseph Lawrence Livermore National Laboratory
More information