Plasma Breakdown Analysis in JFT-2M without the Use of Center Solenoid
|
|
- Clementine Carson
- 5 years ago
- Views:
Transcription
1 3st EPS Conference on Plasma Physics 28th June 2nd July, 24, Imperial College, London Plasma Breakdown Analysis in without the Use of Center Solenoid H. Tsutsui, S. Tsuji-Iio, R. Shimada, M. Sato, K. Tsuzuki, Y. Kusama, H. Kimura Research Laboratory for Nuclear Reactors Tokyo Institute of Technology Naka Fusion Research Establishment Japan Atomic Energy Research Institute
2 Introduction In order to demonstrate compatibility between the low activation ferritic steel (such as F82H) and plasma, performed the Advanced Material Tokamak EXperiment (AMTEX) program. Measurements of permeability in a perpendicular direction of magnetic field Measurements of a breakdown characteristic (required loop voltage and neutral gas pressure) with the ferritic steel. A numerical investigation of the breakdown characteristic
3 Measurement of F82H Magnetization magnetization of the ferritic steel is measured. B = µ H + M B M ( H ) ( H = µ + ) p H p Tokamak Toroidal Field Poloidal Field Coil Vertical Field(<5T) Toroidal Field Equivalent permeability µ p
4 Measurement of Magnetization (Results) Magnetic Flux Density, Bp[T] 2 - µ H T-eff [T] Manetic Field Intensity, Hp[A/m] B ext = T µ P /µ Measurement Calculation µ H T-eff [T] It was found that the equivalent permeability µ p in the poloidal direction follows the theory.
5 Breakdown Experiment Using only TF coils and S coils, relations of a neutral gas pressure and a required voltage for a breakdown were measured. OH coil does not work!! Toroidal field was changed to check an effect of the ferritic steel. (µ Cross Section of
6 Breakdown Experiment (Results) Breakdown characteristics were measured aginst the toroidal field strengths of.6t.6t.3t. Succeeded and failed cases are marked with and, respectively. The minimum neutral gas pressure required for breakdown exists. Under the pressure, the required voltage increases abruptly or a breakdown does not occur. This result qualitatively agrees with the experiments of JFT-2 and a conventional breakdown theory. V B D (V) B t =.6 T B t =.3 T B t =.6 T P(Pa)
7 Breakdown and Plasma Formation Breakdown Plasma Formation Current Ramp Up n e V Loop I P Breakdown Electron-neutral gas collisions are dominant (Avalanche ionization<. model by Townsend) Plasma Formation Tim e Electron-Ion collisions have to be considered including the thermal motion of electrons Electromagnetic field by plasma current is negligible
8 Simulation Collision Ionization Model collision Electron-neutral gas collisions are dominant when ionization >., breakdown is succeeded. Electron-Ion collisions are included Electromagnetic field by plasma current is negligible E [V/m] <v>=v d <v>= P [Pa] L=3[m] Application for JT-6U A insulation in the toroidal direction is introduced. An effect of iron core is included by a modification of inductance.
9 Basic Equations n t e eµ v α = d µ = + ( n v ) = αv νi v d = e( E + v B) e m ν e p n e d d e Townsend Coefficient d Mobility Drift Approximation ψ + d = V t E l E = η j = j en µ e 2 ψ ( x) = G( x, x') j ( x') d x' ϕ nw e t 3 2 e + ( nwv ) = j E n ν W kt = W mv 2 2 B e e d e e d e Shifted MaxwelIian i i ν ν i p i = = n target i ( T, v ) ν i= elastic < σ v i + > i elastic e e d Wiν i W + ν I
10 Elementary Process
11 Dependence of Ve, α on E/P in Static Model 6 He V e [m/s] 5 4 H E/P [V/m/Pa] -4. E/P [V/m/Pa] Solid Lines: Static Model Dashed Lines: Experiments with electrodes
12 2-D Simulation Code PF Coils Plasma 2 Vacuum Vessel
13 Insulation in the toroidal direction obtains a loop resistance by a toroidal insulation. I I 2 Vacuum Vessel R G In order to simulate the toroidal insulation, a gap resistance R G is inserted among coils which simulate a vacuum vessel. I G = n I n V V = R G I G
14 An iron core scarcely affects a poloidal field in a vacuum vessel. r It is assumed that a iron core, which is sufficiently fine and long, exists on the Z axis. r 2 A inductance is modified to include a magnetic flux in the iron core. M ( r, r ) 2 = µ χ 2 m πa r r 3 2 a χ m relative permeability
15 Results of Simulations Using the 2D-simulation code with the modifications for without the ferritic steel, time evolutions of ionization are computed. Effects of the toroidal gap and the iron core are investigated.... n e /n e-6 e-8 e- B T =.6T, W/O core, cut B T =.6T, W core, W/O cut B T =.6T, W core, cut B T =.6T, W core, cut..2 Time [s] The iron core and toroidal gap are required for the breakdown.
16 Results of Simulations (2) Using the modified simulation code, we calculated the relations of breakdown voltages and gas pressures. Comparing the simulation with the experiments, the range of neutral gas pressure for the breakdown is narrow, and the voltages become low. Effects of toroidal field has not yet obtained. 2 5 V loop [V] 5 B T =.3T(Exp) B T =.6T(Exp) B T =.6T(Exp) B T =.6T(Sim) P[Pa] It is needed that more detail investigation of calculation results and a modification of a simulation model.
17 Configurations at Breakdown B T =.6T P=5x -3 Electron Density Current Density Poloidal Flux 2 Closed magnetic surfaces are produced and a breakdown happens there. Distributions of electron and current densities are not overlapped.
18 Time Evolution in Breakdown Failure B T =.6T P=5x -3 Pa t =.6x -3 ms t =.2x -3 ms t =.8x -3 ms t =.24x -3 ms A breakdown was failed in spite of the production of closed magnetic surfaces.
19 Conclusion The equivalent permeability in the poloidal direction was measured. The usual theory is confirmed. Breakdown characteristics (voltage and pressure) were experimentally investigated. Dependences on the toroidal fields B T =.6T,.6T,.3T are obtained. Breakdown voltage decreases with the toroidal field strength. Modifying the simulation code for, computation results are compared with the experiments. The toroidal gap and the iron core are required for the breakdown. Quantitative agreements between the experiments and the simulation are not obtained. More modification of the code is needed.
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 informationJacob s Ladder Controlling Lightning
Host: Fusion specialist: Jacob s Ladder Controlling Lightning PART 1 Jacob s ladder demonstration Video Teacher resources Phil Dooley European Fusion Development Agreement Peter de Vries European Fusion
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 informationEvolution 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(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 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 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 informationD.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706
D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 Concept Overview Implementation on PEGASUS Results Current
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 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 informationComparison of plasma breakdown with a carbon and ITER-like wall
Comparison of plasma breakdown with a carbon and ITER-like wall P.C. de Vries, A.C.C. Sips, H.T. Kim, P.J. Lomas, F. Maviglia, R. Albanese, I. Coffey, E. Joffrin, M. Lehnen, A. Manzanares, M. O Mulane,
More informationRipple Loss of Alpha Particles in a Low-Aspect-Ratio Tokamak Reactor
P Ripple Loss of Alpha Particles in a Low-Aspect-Ratio Tokamak Reactor K. TANI, S. NISHIO, K. TOBITA, H. TSUTSUI *, H. MIMATA *, S. TSUJI-IIO *, T. AOKI * Japan Atomic Energy Agency, tani.keiji@jaea.go.jp
More informationComputational Study of Non-Inductive Current Buildup in Compact DEMO Plant with Slim Center Solenoid
1st IAEA TM, First Generation of Fusion Power Plants Design and Technology -, Vienna, July 5-7, 25 Computational Study of Non-Inductive Current Buildup in Compact DEMO Plant with Slim Center Solenoid Y.
More informationRotation and Neoclassical Ripple Transport in ITER
Rotation and Neoclassical Ripple Transport in ITER Elizabeth J. Paul 1 Matt Landreman 1 Francesca Poli 2 Don Spong 3 Håkan Smith 4 William Dorland 1 1 University of Maryland 2 Princeton Plasma Physics
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 informationD.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706
D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706 Non-solenoidal startup using point-source DC helicity injectors
More informationEvolution 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 informationAdvancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment
Advancing Toward Reactor Relevant Startup via Localized Helicity Injection at the Pegasus Toroidal Experiment E. T. Hinson J. L. Barr, M. W. Bongard, M. G. Burke, R. J. Fonck, J. M. Perry, A. J. Redd,
More informationToward 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 informationDT 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 informationLecture 24. April 5 th, Magnetic Circuits & Inductance
Lecture 24 April 5 th, 2005 Magnetic Circuits & Inductance Reading: Boylestad s Circuit Analysis, 3 rd Canadian Edition Chapter 11.1-11.5, Pages 331-338 Chapter 12.1-12.4, Pages 341-349 Chapter 12.7-12.9,
More informationFormation of An Advanced Tokamak Plasma without the Use of Ohmic Heating Solenoid in JT-60U
1 Formation of An Advanced Tokamak Plasma without the Use of Ohmic Heating Solenoid in JT-60U Y. Takase, 1) S. Ide, 2) S. Itoh, 3) O. Mitarai, 4) O. Naito, 2) T. Ozeki, 2) Y. Sakamoto, 2) S. Shiraiwa,
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 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 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 informationPhysics 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 informationAbstract. The Pegasus Toroidal Experiment is an ultra-low aspect ratio (A < 1.2) spherical tokamak (ST) capable of operating in the high I N
Abstract The Pegasus Toroidal Experiment is an ultra-low aspect ratio (A < 1.2) spherical tokamak (ST) capable of operating in the high I N regime (I N > 12). Access to this regime requires a small centerpost
More informationReduced-Size LHD-Type Fusion Reactor with D-Shaped Magnetic Surface )
Reduced-Size LHD-Type Fusion Reactor with D-Shaped Magnetic Surface ) Tsuguhiro WATANABE National Institute for Fusion Science, Toki 509-59, Japan (Received 6 December 011 / Accepted 1 June 01) A new winding
More informationEnergetic-Ion-Driven MHD Instab. & Transport: Simulation Methods, V&V and Predictions
Energetic-Ion-Driven MHD Instab. & Transport: Simulation Methods, V&V and Predictions 7th APTWG Intl. Conference 5-8 June 2017 Nagoya Univ., Nagoya, Japan Andreas Bierwage, Yasushi Todo 14.1MeV 10 kev
More informationNeoclassical transport
Neoclassical transport Dr Ben Dudson Department of Physics, University of York Heslington, York YO10 5DD, UK 28 th January 2013 Dr Ben Dudson Magnetic Confinement Fusion (1 of 19) Last time Toroidal devices
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 informationD- 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 informationYuntao, SONG ( ) and Satoshi NISHIO ( Japan Atomic Energy Research Institute
Conceptual design of liquid metal cooled power core components for a fusion power reactor Yuntao, SONG ( ) and Satoshi NISHIO ( Japan Atomic Energy Research Institute Japan-US workshop on Fusion Power
More informationDesign concept of near term DEMO reactor with high temperature blanket
Design concept of near term DEMO reactor with high temperature blanket Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies March 16-18, 2009 Tokyo Univ. Mai Ichinose, Yasushi Yamamoto
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 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 formation in MAST by using the double null merging technique
1 Plasma formation in MAST by using the double null merging technique P. Micozzi 1, F. Alladio 1, P. Costa 1, A. Mancuso 1, A. Sykes 2, G. Cunningham 2, M. Gryaznevich 2, J. Hicks 2, M. Hood 2, G. McArdle
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 informationLecture 6: High Voltage Gas Switches
Lecture 6: High Voltage Gas Switches Switching is a central problem in high voltage pulse generation. We need fast switches to generate pulses, but in our case, they must also hold off high voltages before
More informationUniversity of the Philippines College of Science PHYSICS 72. Summer Second Long Problem Set
University of the Philippines College of Science PHYSICS 72 Summer 2012-2013 Second Long Problem Set INSTRUCTIONS: Choose the best answer and shade the corresponding circle on your answer sheet. To change
More informationDriving 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 informationExperimental 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 informationFundamental Constants
Fundamental Constants Atomic Mass Unit u 1.660 540 2 10 10 27 kg 931.434 32 28 MeV c 2 Avogadro s number N A 6.022 136 7 36 10 23 (g mol) 1 Bohr magneton μ B 9.274 015 4(31) 10-24 J/T Bohr radius a 0 0.529
More informationPredictive Power-Balance Modeling of PEGASUS and NSTX-U Local Helicity Injection Discharges
Predictive Power-Balance Modeling of PEGASUS and NSTX-U Local Helicity Injection Discharges J.L. Barr, M.W. Bongard, M.G. Burke, R.J. Fonck, E.T. Hinson, J.M. Perry, A.J. Redd, D.J. Schlossberg, K.E. Thome
More informationThe initial magnetization curve shows the magnetic flux density that would result when an increasing magnetic field is applied to an initially
MAGNETIC CIRCUITS The study of magnetic circuits is important in the study of energy systems since the operation of key components such as transformers and rotating machines (DC machines, induction machines,
More informationIntroduction to Fusion Physics
Introduction to Fusion Physics Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching DPG Advanced Physics School The Physics of ITER Bad Honnef, 22.09.2014 Energy from nuclear fusion Reduction
More informationIs the Troyon limit a beta limit?
Is the Troyon limit a beta limit? Pierre-Alexandre Gourdain 1 1 Extreme State Physics Laboratory, Department of Physics and Astronomy, University of Rochester, Rochester, NY 14627, USA The plasma beta,
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 informationElectrode 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 informationDEMO Concept Development and Assessment of Relevant Technologies. Physics and Engineering Studies of the Advanced Divertor for a Fusion Reactor
FIP/3-4Rb FIP/3-4Ra DEMO Concept Development and Assessment of Relevant Technologies Y. Sakamoto, K. Tobita, Y. Someya, H. Utoh, N. Asakura, K. Hoshino, M. Nakamura, S. Tokunaga and the DEMO Design Team
More informationMutual Inductance. The field lines flow from a + charge to a - change
Capacitors Mutual Inductance Since electrical charges do exist, electric field lines have a starting point and an ending point. For example, if you have a + and a - change, the field lines would look something
More informationPlasma Start-Up Results with EC Assisted Breakdown on FTU
1 EXW/P2-03 Plasma Start-Up Results with EC Assisted Breakdown on FTU G. Granucci 1), G. Ramponi 1), G. Calabrò 2), F. Crisanti 2), G. Ramogida 2), W. Bin 1), A. Botrugno 2), P.Buratti 2), O. D Arcangelo1,
More informationMaterial, Design, and Cost Modeling for High Performance Coils. L. Bromberg, P. Titus MIT Plasma Science and Fusion Center ARIES meeting
Material, Design, and Cost Modeling for High Performance Coils L. Bromberg, P. Titus MIT Plasma Science and Fusion Center ARIES meeting Tokamak Concept Improvement Cost minimization Decrease cost of final
More informationMatti Laan Gas Discharge Laboratory University of Tartu ESTONIA
Matti Laan Gas Discharge Laboratory University of Tartu ESTONIA Outline 1. Ionisation 2. Plasma definition 3. Plasma properties 4. Plasma classification 5. Energy transfer in non-equilibrium plasma 6.
More informationConfinement of toroidal non-neutral plasma in Proto-RT
Workshop on Physics with Ultra Slow Antiproton Beams, RIKEN, March 15, 2005 Confinement of toroidal non-neutral plasma in Proto-RT H. Saitoh, Z. Yoshida, and S. Watanabe Graduate School of Frontier Sciences,
More informationConfinement of toroidal non-neutral plasma in Proto-RT
Workshop on Physics with Ultra Slow Antiproton Beams, RIKEN, March 15, 2005 Confinement of toroidal non-neutral plasma in Proto-RT H. Saitoh, Z. Yoshida, and S. Watanabe Graduate School of Frontier Sciences,
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 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 informationEquilibrium 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 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 informationDO PHYSICS ONLINE MOTORS AND GENERATORS FARADAY S LAW ELECTROMAGNETIC INDUCTION
DO PHYSICS ONLINE MOTORS AND GENERATORS FARADAY S LAW ELECTROMAGNETIC INDUCTION English Michael Faraday (1791 1867) who experimented with electric and magnetic phenomena discovered that a changing magnetic
More informationMagnetism & Electromagnetism
Magnetism & Electromagnetism By: Dr Rosemizi Abd Rahim Click here to watch the magnetism and electromagnetism animation video http://rmz4567.blogspot.my/2013/02/electrical-engineering.html 1 Learning Outcomes
More informationParticle Pinch Model of Passing/Trapped High-Z Impurity with Centrifugal Force Effect )
Particle Pinch Model of Passing/Trapped High-Z Impurity with Centrifugal Force Effect ) Yusuke SHIMIZU, Takaaki FUJITA, Atsushi OKAMOTO, Hideki ARIMOTO, Nobuhiko HAYASHI 1), Kazuo HOSHINO 2), Tomohide
More informationMicrowave Spherical Torus Experiment and Prospect for Compact Fusion Reactor
Microwave Spherical Torus Experiment and Prospect for Compact Fusion Reactor Takashi Maekawa 1,*, Hitoshi Tanaka 1, Masaki Uchida 1, Tomokazu Yoshinaga 1, Satoshi Nishio 2 and Masayasu Sato 2 1 Graduate
More informationCurrent Drive Experiments in the Helicity Injected Torus (HIT II)
Current Drive Experiments in the Helicity Injected Torus (HIT II) A. J. Redd, T. R. Jarboe, P. Gu, W. T. Hamp, V. A. Izzo, B. A. Nelson, R. G. O Neill, R. Raman, J. A. Rogers, P. E. Sieck and R. J. Smith
More informationDevelopment of Long Pulse Neutral Beam Injector on JT-60U for JT-60SA
Development of Long Pulse Neutral Beam Injector on JT-60U for JT-60SA M.Hanada, Y.Ikeda, L. Grisham 1, S. Kobayashi 2, and NBI Gr. Japan Atomic Energy Agency, 801-1 Mukohyama, Naka, Ibaraki-ken, 311-0193,
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 informationTokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011
Tokamak Divertor System Concept and the Design for ITER Chris Stoafer April 14, 2011 Presentation Overview Divertor concept and purpose Divertor physics General design considerations Overview of ITER divertor
More informationIntroduction to Nuclear Fusion. Prof. Dr. Yong-Su Na
Introduction to Nuclear Fusion Prof. Dr. Yong-Su Na What is a stellarator? M. Otthe, Stellarator: Experiments, IPP Summer School (2008) 2 Closed Magnetic System ion +++ ExB drift Electric field, E - -
More informationPRACTICE EXAM 1 for Midterm 2
PRACTICE EXAM 1 for Midterm 2 Multiple Choice Questions 1) The figure shows three identical lightbulbs connected to a battery having a constant voltage across its terminals. What happens to the brightness
More information2D full wave analysis of wave structure by TASK/WF2
17th NEXT (Numerical Experiment of Tokamak) Meeting, University of Tokyo, Kashiwa, Japan, March 15-16, 2012 2D full wave analysis of wave structure by TASK/WF2 Y. Maruyama, A. Fukuyama Department of Nuclear
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 informationA Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current. John Sarff
A Hybrid Inductive Scenario for a Pulsed- Burn RFP Reactor with Quasi-Steady Current John Sarff 12th IEA RFP Workshop Kyoto Institute of Technology, Kyoto, Japan Mar 26-28, 2007 The RFP fusion development
More informationCOLLEGE PHYSICS Chapter 23 ELECTROMAGNETIC INDUCTION, AC CIRCUITS, AND ELECTRICAL TECHNOLOGIES
COLLEGE PHYSICS Chapter 23 ELECTROMAGNETIC INDUCTION, AC CIRCUITS, AND ELECTRICAL TECHNOLOGIES Induced emf: Faraday s Law and Lenz s Law We observe that, when a magnet is moved near a conducting loop,
More informationSpherical Torus Fusion Contributions and Game-Changing Issues
Spherical Torus Fusion Contributions and Game-Changing Issues Spherical Torus (ST) research contributes to advancing fusion, and leverages on several game-changing issues 1) What is ST? 2) How does research
More informationTRANSFORMERS B O O K P G
TRANSFORMERS B O O K P G. 4 4 4-449 REVIEW The RMS equivalent current is defined as the dc that will provide the same power in the resistor as the ac does on average P average = I 2 RMS R = 1 2 I 0 2 R=
More informationAdvanced 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 informationCapability Assessment of the Equilibrium Field System in KTX
Plasma Science and Technology, Vol.18, No.1, Jan. 216 Capability Assessment of the Equilibrium Field System in KTX LUO Bing ( ) 1, LUO Zhengping ( ) 2, XIAO Bingjia ( ) 2,3, YOU Wei ( ) 1, TAN Mingsheng
More informationPHYS 1442 Section 004 Lecture #14
PHYS 144 Section 004 Lecture #14 Wednesday March 5, 014 Dr. Chapter 1 Induced emf Faraday s Law Lenz Law Generator 3/5/014 1 Announcements After class pickup test if you didn t Spring break Mar 10-14 HW7
More informationMAGNETIC NOZZLE PLASMA EXHAUST SIMULATION FOR THE VASIMR ADVANCED PROPULSION CONCEPT
MAGNETIC NOZZLE PLASMA EXHAUST SIMULATION FOR THE VASIMR ADVANCED PROPULSION CONCEPT ABSTRACT A. G. Tarditi and J. V. Shebalin Advanced Space Propulsion Laboratory NASA Johnson Space Center Houston, TX
More informationRWM 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 informationPhysics 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 informationBook Page cgrahamphysics.com Transformers
Book Page 444-449 Transformers Review The RMS equivalent current is defined as the dc that will provide the same power in the resistor as the ac does on average P average = I 2 RMS R = 1 2 I 0 2 R= V RMS
More information1 FT/P7-35 Technological and Environmental Prospects of Low Aspect Ratio Tokamak Reactor VECTOR Abstract. 1. Introduction
1 Technological and Environmental Prospects of Low Aspect Ratio Tokamak Reactor VECTOR S. NISHIO 1), K. TOBITA 1), K. TOKIMATSU 2), K. SHINYA 3), I. SENDA 3), T. ISONO 1), Y. NAKAMURA 1), M. SATO 1), S.
More informationPerspective on Fusion Energy
Perspective on Fusion Energy Mohamed Abdou Distinguished Professor of Engineering and Applied Science (UCLA) Director, Center for Energy Science & Technology (UCLA) President, Council of Energy Research
More informationElectromagnetism and Light
Electromagnetism and Light Monday Properties of waves (sound and light) interference, diffraction [Hewitt 12] Tuesday Light waves, diffraction, refraction, Snell's Law. [Hewitt 13, 14] Wednesday Lenses,
More informationPhysics of fusion power. Lecture 13 : Diffusion equation / transport
Physics of fusion power Lecture 13 : Diffusion equation / transport Many body problem The plasma has some 10 22 particles. No description is possible that allows for the determination of position and velocity
More informationCode No: RR Set No. 1
Code No: RR410209 Set No. 1 1. What are the gases mainly used in insulating medium at high pressures? Which is more suitable? Why? What about its dielectric strength? Explain. [16] 2. (a) Define time lags
More informationComparison of plasma breakdown with a carbon and ITER-like wall
1 EXD/4-2 Comparison of plasma breakdown with a carbon and ITER-like wall P.C. de Vries 1), A.C.C. Sips 2,3), H.T. Kim 4,5), P.J. Lomas 4), F. Maviglia 6), R. Albanese 6), I. Coffey 7), E. Joffrin 8),
More informationCurrent-driven instabilities
Current-driven instabilities Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 21 st February 2014 Ben Dudson Magnetic Confinement Fusion (1 of 23) Previously In the last
More informationElectrical Discharges Characterization of Planar Sputtering System
International Journal of Recent Research and Review, Vol. V, March 213 ISSN 2277 8322 Electrical Discharges Characterization of Planar Sputtering System Bahaa T. Chaid 1, Nathera Abass Ali Al-Tememee 2,
More informationElectromagnetic Field Theory (EMT) Lecture # 25
Electromagnetic Field Theory (EMT) Lecture # 25 1) Transformer and Motional EMFs 2) Displacement Current 3) Electromagnetic Wave Propagation Waves & Applications Time Varying Fields Until now, we have
More informationAdditional Heating Experiments of FRC Plasma
Additional Heating Experiments of FRC Plasma S. Okada, T. Asai, F. Kodera, K. Kitano, T. Suzuki, K. Yamanaka, T. Kanki, M. Inomoto, S. Yoshimura, M. Okubo, S. Sugimoto, S. Ohi, S. Goto, Plasma Physics
More informationModelling 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 informationModélisation de sources plasma froid magnétisé
Modélisation de sources plasma froid magnétisé Gerjan Hagelaar Groupe de Recherche Energétique, Plasma & Hors Equilibre (GREPHE) Laboratoire Plasma et Conversion d Énergie (LAPLACE) Université Paul Sabatier,
More informationPhysics 106, Section 1
Physics 106, Section 1 Magleby Exam 2, Summer 2012 Exam Cid You are allowed a pencil and a testing center calculator. No scratch paper is allowed. Testing center calculators only. 1. A circular coil lays
More informationPreliminary experiment of plasma current startup by ECR wave on SUNIST spherical tokamak
The 3 rd IAEA TCM on Spherical Torus and the 11 th STW, St. Petersburg Preliminary experiment of plasma current startup by ECR wave on spherical tokamak HE Yexi, ZHANG Liang, *FENG Chunhua, FU Hongjun,
More information15 Inductance solenoid, shorted coax
z 15 nductance solenoid, shorted coax 3 Given a current conducting path C, themagneticfluxψ linking C can be expressed as a function of current circulating around C. 2 1 Ψ f the function is linear, i.e.,
More information0 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 informationIon and Electron Heating Characteristics of Magnetic Reconnection in TS-3 and UTST Merging Startup Experiments
Ion and Electron Heating Characteristics of Magnetic Reconnection in TS-3 and UTST Merging Startup Experiments Y. Ono 1), R. Imazawa 1), H. Imanaka 1), Y. Hayashi 1), S. Ito 1), M. Nakagawa 1), T. Yamada
More information