Plasma Physics and Fusion Energy Research

Size: px
Start display at page:

Download "Plasma Physics and Fusion Energy Research"

Transcription

1 Plasma Physics and Fusion Energy Research Paddy Mc Carthy, Physics Department, UCC, 1/11/2011 Research Group: Plasma Data Analysis Group: PhD Students: MSc Students: P. J. Mc Carthy (Group Leader) R. Armstrong (Visiting Researcher) Diarmuid Curran Mike Dunne (TCD graduate!) Tom O Gorman Brendan Cahill Shane O Mahony Funders: Euratom, Max Planck Institut für Plasmaphysik, Munich TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

2 Lecture Outline: Plasma Overview Fusion Energy and Tokamaks How the Tokamak overcomes particle drift in a closed axisymmetric system Research topics in UCC Fusion in Europe and further afield TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

3 What is a plasma? Plasmas are conductive assemblies of charged particles, neutrals and fields that exhibit collective effects, carry electrical currents and generate magnetic fields. TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

4 Why are we interested in! Fusion Energy plasmas?! Potential source of safe, clean, and abundant energy.! Astrophysics! Understanding plasmas helps us understand stars and stellar evolution.! Plasma Applications! Plasmas can be used to build computer chips and to clean up toxic waste. TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

5 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011 per nucleon

6 !" Fission is easiest at low energies; cross-section is maximum here!" Fusion is vanisingly unlikely at low energies; cross-section is miniscule TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

7 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

8 Puzzle: T = 1keV at centre of sun. Proton-Proton Coloumb Barrier height: How can 1 kev protons overcome a 1 MeV barrier? Answer: (Gamow, 1930) Quantum Tunnelling TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

9 Relevant Fusion Reactions in the Laboratory 1D D 2 2 He3 (0.82 MeV) + n (2.5MeV) 1T 3 (1 MeV) + p (3 MeV) 1 D2 + 2 He 3 2 He4 (3.6 MeV) + p (14.7MeV) 1D T 3 2He 4 (3.5 MeV) + n (14.1MeV) 3 Li6 (7.4%) + n 2 He4 + 1 T MeV 3 Li7 (92.6%) + n 2 He4 + 1 T3 + n 2.8 MeV TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

10 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011 " 3#10 20 s m $3

11 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

12 Fusion Energy - Advantages It promises a large-scale energy source with basic fuels which are abundant and available everywhere; Very low global impact on the environment no CO2 greenhouse gas emissions; Day-to-day-operation of a fusion power station would not require the transport of radio-active materials;power stations would be inherently safe, with no possibility of meltdown or runaway reactions ; There is no long-lasting radioactive waste to create a burden on future generations; While development and capital investment costs are high, the marginal cost of supply is expected to be negligible compared to that of energy derived from fossil fuels. TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

13 Fusion Energy - Disadvantages Fusion reaction is difficult to initiate High temperatures (millions of degrees) in a clean, high vacuum environment are required; Technically complex and high capital cost reactors are needed More research and development needed to bring concept to fruition The physics is well advanced, but but technological and material challenges requiring a multi-decade sustained effort must be overcome. TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

14 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

15 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

16 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

17 !! Donut shape Unlike mirror, no end losses because the field lines go around and close on themselves! But major problem with particle drift if magnetic field lines are circular in form. Tokamak TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011 Schematic picture of the tokamak

18 Particle Drift Recap General expression for the drift velocity of the guiding centres of particles of charge q in a uniform B field and sub ject to an additional force F: Gyration Grad-B and curvature drifts Parallel motion Pololarization drift ExB drift TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

19 Insight into drift motion Trajectories of a 75 ev electron in a B! field of 1 mt and E # fields of 0 (top), 150 V/m (middle) and 1500 V/m (bottom). TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011 Left/right half-orbits are symmetric, but updown half-orbits are strongly asymmetric => particle travels more to right than to left.

20 Toroidal curvature* Toroidal magnetic field coils! The toroidal magnetic field follows form! And therefore varies with major radius R as Top down view of the tokamak TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011 Next 5 slides based on Warwick University Physics of Fusion Power course

21 Toroidal curvature! The toroidal magnetic field has a gradient! Which leads to a combined curvature and!b drift in the vertical direction: From TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011 we get Note that the sign of the drift depends on the sign of the charge q ˆ R " ˆ Z ˆ 0 B 0 # B R 0 0

22 Toroidal curvature! The drift!!! Leads to charge separation Build up of an electric field (calculate through the balance with polarization) And then to an ExB velocity Poloidal cut of the tokamak. TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

23 Toroidal curvature has its price! The ExB velocity! Is directed outward and will move the plasma on the wall in a short timescale (µs) Poloidal cut of the tokamak. TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

24 Remedy : a plasma current! A toroidal current in the plasma will generate a poloidal field (field lines short way round)! Combined toroidal and poloidal fields make helical field lines so that all particle orbits sample top/inside/bottom/outside regions.! Vertical!B drift still present, but helical field lines short out any tendency towards charge separation by accelerating electrons along the field line to maintain charge neutrality.! Charge separation no longer occurs and particles are well confined. The field lines wind around helically. TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

25 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

26 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

27 Blick in das Plasmagefäß von ASDEX Upgrade

28 Cross-section of ASDEX Upgrade tokamak showing toroidal and poloidal field coils TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

29

30 PDAG List of Collaborative Projects & Research Topics ASDEX Upgrade Project CLISTE Interpretive Equilibrium Code Function Parameterization MHD activity analysis to improve q profile identification Thomson Scattering analysis: ECE comparison Wendelstein 7-X Project Fast recovery of W7-X equilibria Transport and spectroscopy experiments using a DP machine ITER diagnostic design studies: Group involvement in Integrated Tokamak Modelling Taskforce TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

31 100 kpa Fluid Pressure v. minor radius Z! R jxb -!p Fluid pressure gradient (outward force/v) balances inward pinch force/v: jxb =!p Axisymmetry of tokamak simplifies jxb =!p: TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011 Grad-Shafranov equation: scalar, weakly nonlinear PDE

32 Interpretive Equilibria: Finding an equilibium to match data! Regularize source profiles: choose a functional form with a reasonable number of free parameters! Flexible form very desirable. Good choice: Cubic Splines! Initialize to a default current distribution (centred in vessel)! (i) Solve Poisson-like linear PDE for trial Jtor (R,Z) by a least squares best fit to input experimental data which must be expressible as a linear function of the free parameters! (ii) Construct updated flux function and find new plasma boundary (we are solving a free boundary problem)! (iii) Construct updated Jtor (R,Z) using updated flux surface topology and free parameter values.! Iterate steps (i)-(iii) until a convergence criterion is met Interpretive Tokamak Equilibrium at IPP Garching: CLISTE TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

33 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

34 Physics & Astronomy Society, UCC TCD Graduate 31/1/2006 Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

35 Equilibrium Magnetics only 12-knot spline model (28 fit parameters) flux loops B probes MSE Ped.Pres. J B neo " n e dl I SOL E18 ROE 13kA #17151, 3.850s TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

36 Magnetics & Q=1 & DCN+LID & ROE & MSE & YAR fit flux loops B probes MSE Ped.Pres. J B neo " n e dl I SOL E18 ROE 0.5 ka #17151, 3.850s TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

37 The Wendelstein 7-X Stellarator (under construction in Greifswald) TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

38 Physics & Astronomy Society, UCC 31/1/2006

39 Physics & Astronomy Society, UCC 31/1/2006

40 Physics & Astronomy Society, UCC 31/1/2006

41 Physics & Astronomy Society, UCC 31/1/2006

42

43

44 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

45 n e =1.1e17 m -3 T e =0.6eV P He =9.6e-3mb

46 n e =1.5e17 m -3 T e =0.4eV P He =1.2e-2mb

47 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

48 Four decades of progress in achieving confinement times* leading to scientific breakeven * " E = (3/2) p dv # Heating Power Physics & Astronomy Society, UCC 31/1/2006

49 The Future of Fusion Energy Research: ITER" ITER, the International Tokamak Experimental Reactor is being constructed at Cadarache, near Aix en Provence, on a 10 year timeframe for c. #7.5bn and will operate for c. 25 y at projected running costs of #7.5bn. " SSP TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

50 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

51 TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

52 R. Aymar, Nobel Symposium Stockholm, 2005

53 Summary Fusion offers one of the greatest hopes for a long-term solution to the problem of a viable, environmentally friendly source for the world s future energy needs. Fusion research is carried out within the framework of plasma physics, a key current area of both fundamental and applied research. At UCC, we participate (both on and off-campus) in experiments at major fusion labs in Germany and the U.K. as well as in ITER design activities. TCD Graduate Plasma Physics Module PY5012 Guest Lecture 1 st Nov 2011

Plasma Physics and Fusion Energy Research

Plasma Physics and Fusion Energy Research Coláiste na hollscoile Corcaigh University College Cork Plasma Physics and Fusion Energy Research Plasma Data Analysis Group: Graduate Student: Paddy Mc Carthy Sean Knott (PhD) (Group Leader) (Co-supervisor:

More information

Introduction to Fusion Physics

Introduction 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 information

Chapter IX: Nuclear fusion

Chapter IX: Nuclear fusion Chapter IX: Nuclear fusion 1 Summary 1. General remarks 2. Basic processes 3. Characteristics of fusion 4. Solar fusion 5. Controlled fusion 2 General remarks (1) Maximum of binding energy per nucleon

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

The Dynomak Reactor System

The Dynomak Reactor System The Dynomak Reactor System An economically viable path to fusion power Derek Sutherland HIT-SI Research Group University of Washington November 7, 2013 Outline What is nuclear fusion? Why do we choose

More information

Introduction to Nuclear Fusion. Prof. Dr. Yong-Su Na

Introduction 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 information

INTRODUCTION TO MAGNETIC NUCLEAR FUSION

INTRODUCTION TO MAGNETIC NUCLEAR FUSION INTRODUCTION TO MAGNETIC NUCLEAR FUSION S.E. Sharapov Euratom/CCFE Fusion Association, Culham Science Centre, Abingdon, Oxfordshire OX14 3DB, UK With acknowledgments to B.Alper for use of his transparencies

More information

The Path to Fusion Energy creating a star on earth. S. Prager Princeton Plasma Physics Laboratory

The Path to Fusion Energy creating a star on earth. S. Prager Princeton Plasma Physics Laboratory The Path to Fusion Energy creating a star on earth S. Prager Princeton Plasma Physics Laboratory The need for fusion energy is strong and enduring Carbon production (Gton) And the need is time urgent Goal

More information

Configuration Optimization of a Planar-Axis Stellarator with a Reduced Shafranov Shift )

Configuration 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 information

Stellarators. Dr Ben Dudson. 6 th February Department of Physics, University of York Heslington, York YO10 5DD, UK

Stellarators. Dr Ben Dudson. 6 th February Department of Physics, University of York Heslington, York YO10 5DD, UK Stellarators Dr Ben Dudson Department of Physics, University of York Heslington, York YO10 5DD, UK 6 th February 2014 Dr Ben Dudson Magnetic Confinement Fusion (1 of 23) Previously... Toroidal devices

More information

Controlled Thermonuclear Fusion

Controlled Thermonuclear Fusion Controlled Thermonuclear Fusion Roscoe White Plasma Physics Laboratory, Princeton University The promise of cheap clean energy Consistently twenty years off, for the last 60 years Research began at Princeton

More information

Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan

Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan The Sun Magnetic Confinement Fusion and Tokamaks Chijin Xiao Department of Physics and Engineering Physics University of Saskatchewan 2017 CNS Conference Niagara Falls, June 4-7, 2017 Tokamak Outline Fusion

More information

Introduction to Plasma Physics

Introduction to Plasma Physics Introduction to Plasma Physics Hartmut Zohm Max-Planck-Institut für Plasmaphysik 85748 Garching DPG Advanced Physics School The Physics of ITER Bad Honnef, 22.09.2014 A simplistic view on a Fusion Power

More information

Generating of fusion plasma neutron source with AFSI for Serpent MC neutronics computing Serpent UGM 2015 Knoxville, TN,

Generating of fusion plasma neutron source with AFSI for Serpent MC neutronics computing Serpent UGM 2015 Knoxville, TN, Generating of fusion plasma neutron source with AFSI for Serpent MC neutronics computing Serpent UGM 2015 Knoxville, TN, 14.10.2015 Paula Sirén VTT Technical Research Centre of Finland, P.O Box 1000, 02044

More information

Magnetic Confinement Fusion-Status and Challenges

Magnetic Confinement Fusion-Status and Challenges Chalmers energy conference 2012 Magnetic Confinement Fusion-Status and Challenges F. Wagner Max-Planck-Institute for Plasma Physics, Greifswald Germany, EURATOM Association RLPAT St. Petersburg Polytechnic

More information

Turbulence and Transport The Secrets of Magnetic Confinement

Turbulence and Transport The Secrets of Magnetic Confinement Turbulence and Transport The Secrets of Magnetic Confinement Presented by Martin Greenwald MIT Plasma Science & Fusion Center IAP January 2005 FUSION REACTIONS POWER THE STARS AND PRODUCE THE ELEMENTS

More information

New Schemes for Confinement of Fusion Products in Stellarators

New Schemes for Confinement of Fusion Products in Stellarators New Schemes for Confinement of Fusion Products in Stellarators W.A. Cooper ), M.Yu. Isaev 1), M.F. Heyn 5), V.N. Kalyuzhnyj 3), S.V. Kasilov 3), W. Kernbichler 5), A.Yu. Kuyanov 1), M.I. Mikhailov 1),

More information

Toroidal confinement devices

Toroidal confinement devices Toroidal confinement devices Dr Ben Dudson Department of Physics, University of York, Heslington, York YO10 5DD, UK 24 th January 2014 Dr Ben Dudson Magnetic Confinement Fusion (1 of 20) Last time... Power

More information

The Virial Theorem, MHD Equilibria, and Force-Free Fields

The Virial Theorem, MHD Equilibria, and Force-Free Fields The Virial Theorem, MHD Equilibria, and Force-Free Fields Nick Murphy Harvard-Smithsonian Center for Astrophysics Astronomy 253: Plasma Astrophysics February 10 12, 2014 These lecture notes are largely

More information

Plasma & Fusion on Earth: merging age-old natural phenomena into your present and future

Plasma & Fusion on Earth: merging age-old natural phenomena into your present and future Plasma & Fusion on Earth: merging age-old natural phenomena into your present and future Presented by Rick Lee Chief Operator, DIII-D Operations Manager, Energy/Fusion Outreach Program General Atomics

More information

Nuclear Fusion 1 of 24 Boardworks Ltd 2011

Nuclear Fusion 1 of 24 Boardworks Ltd 2011 Nuclear Fusion 1 of 24 Boardworks Ltd 2011 2 of 24 Boardworks Ltd 2011 How do we get energy from atoms? 3 of 24 Boardworks Ltd 2011 Energy is produced from atoms in power stations using the process of

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

A Faster Way to Fusion

A Faster Way to Fusion A Faster Way to Fusion 2017 Tokamak Energy Tokamak Energy Ltd Company Overview April 2018 Our Mission To deliver to mankind a cheap, safe, secure and practically limitless source of clean energy fusion

More information

Observation of Neo-Classical Ion Pinch in the Electric Tokamak*

Observation 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 information

Toroidal confinement of non-neutral plasma. Martin Droba

Toroidal confinement of non-neutral plasma. Martin Droba Toroidal confinement of non-neutral plasma Martin Droba Contents Experiments with toroidal non-neutral plasma Magnetic surfaces CNT and IAP-high current ring Conclusion 2. Experiments with toroidal non-neutral

More information

On existence of resistive magnetohydrodynamic equilibria

On existence of resistive magnetohydrodynamic equilibria arxiv:physics/0503077v1 [physics.plasm-ph] 9 Mar 2005 On existence of resistive magnetohydrodynamic equilibria H. Tasso, G. N. Throumoulopoulos Max-Planck-Institut für Plasmaphysik Euratom Association

More information

Jacob s Ladder Controlling Lightning

Jacob 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 information

Active MHD Control Needs in Helical Configurations

Active MHD Control Needs in Helical Configurations Active MHD Control Needs in Helical Configurations M.C. Zarnstorff 1 Presented by E. Fredrickson 1 With thanks to A. Weller 2, J. Geiger 2, A. Reiman 1, and the W7-AS Team and NBI-Group. 1 Princeton Plasma

More information

Electron temperature barriers in the RFX-mod experiment

Electron temperature barriers in the RFX-mod experiment Electron temperature barriers in the RFX-mod experiment A. Scaggion Consorzio RFX, Padova, Italy Tuesday 5 th October 2010 ADVANCED PHYSICS LESSONS 27/09/2010 07/10/2010 IPP GARCHING JOINT EUROPEAN RESEARCH

More information

Is the Troyon limit a beta limit?

Is 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 information

Neoclassical transport

Neoclassical 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 information

Nuclear Fusion Energy Research at AUB Ghassan Antar. Physics Department American University of Beirut

Nuclear Fusion Energy Research at AUB Ghassan Antar. Physics Department American University of Beirut Nuclear Fusion Energy Research at AUB Ghassan Antar Physics Department American University of Beirut Laboratory for Plasma and Fluid Dynamics [LPFD) Students: - R. Hajjar [Physics] - L. Moubarak [Physics]

More information

Chapter 12. Magnetic Fusion Toroidal Machines: Principles, results, perspective

Chapter 12. Magnetic Fusion Toroidal Machines: Principles, results, perspective Chapter 12 Magnetic Fusion Toroidal Machines: Principles, results, perspective S. Atzeni May 10, 2010; rev.: May 16, 2012 English version: May 17, 2017 1 Magnetic confinement fusion plasmas low density

More information

and expectations for the future

and expectations for the future 39 th Annual Meeting of the FPA 2018 First operation of the Wendelstein 7-X stellarator and expectations for the future Hans-Stephan Bosch Max-Planck-Institut für Plasmaphysik Greifswald, Germany on behalf

More information

Der Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk

Der Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk Max-Planck-Institut für Plasmaphysik Der Stellarator Ein alternatives Einschlusskonzept für ein Fusionskraftwerk Robert Wolf robert.wolf@ipp.mpg.de www.ipp.mpg.de Contents Magnetic confinement The stellarator

More information

Physics & Engineering Physics University of Saskatchewan. Supported by NSERC, CRC

Physics & Engineering Physics University of Saskatchewan. Supported by NSERC, CRC Fusion Energy Chijin Xiao and Akira Hirose Plasma Physics laboratory Physics & Engineering Physics University of Saskatchewan Supported by NSERC, CRC Trends in Nuclear & Medical Technologies April il6-7,

More information

PLASMA: WHAT IT IS, HOW TO MAKE IT AND HOW TO HOLD IT. Felix I. Parra Rudolf Peierls Centre for Theoretical Physics, University of Oxford

PLASMA: WHAT IT IS, HOW TO MAKE IT AND HOW TO HOLD IT. Felix I. Parra Rudolf Peierls Centre for Theoretical Physics, University of Oxford 1 PLASMA: WHAT IT IS, HOW TO MAKE IT AND HOW TO HOLD IT Felix I. Parra Rudolf Peierls Centre for Theoretical Physics, University of Oxford 2 Overview Why do we need plasmas? For fusion, among other things

More information

JET and Fusion Energy for the Next Millennia

JET and Fusion Energy for the Next Millennia JET and Fusion Energy for the Next Millennia JET Joint Undertaking Abingdon, Oxfordshire OX14 3EA JG99.294/1 Talk Outline What is Nuclear Fusion? How can Fusion help our Energy needs? Progress with Magnetic

More information

Model 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 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 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

1) H-mode in Helical Devices. 2) Construction status and scientific objectives of the Wendelstein 7-X stellarator

1) H-mode in Helical Devices. 2) Construction status and scientific objectives of the Wendelstein 7-X stellarator Max-Planck-Institut für Plasmaphysik 1) H-mode in Helical Devices M. Hirsch 1, T. Akiyama 2, T.Estrada 3, T. Mizuuchi 4, K. Toi 2, C. Hidalgo 3 1 Max-Planck-Institut für Plasmaphysik, EURATOM-Ass., D-17489

More information

Charged particle motion in external fields

Charged particle motion in external fields Chapter 2 Charged particle motion in external fields A (fully ionized) plasma contains a very large number of particles. In general, their motion can only be studied statistically, taking appropriate averages.

More information

EX8/3 22nd IAEA Fusion Energy Conference Geneva

EX8/3 22nd IAEA Fusion Energy Conference Geneva P.C. de Vries JET-EFDA Culham Science Centre Abingdon OX14 3DB UK EX8/3 22nd IAEA Fusion Energy Conference Geneva P.C. de Vries1, E. Joffrin2,3, M. Brix1, C.D. Challis1, K. Crombé4, B. Esposito5, N.C.

More information

Performance, Heating, and Current Drive Scenarios of ASDEX Upgrade Advanced Tokamak Discharges

Performance, Heating, and Current Drive Scenarios of ASDEX Upgrade Advanced Tokamak Discharges Performance, Heating, and Current Drive Scenarios of ASDEX Upgrade Advanced Tokamak Discharges R. C. Wolf, J. Hobirk, G. Conway, O. Gruber, A. Gude, S. Günter, K. Kirov, B. Kurzan, M. Maraschek, P. J.

More information

The extrapolation of the experimentally measured energy confinement time in existing tokamaks towards ITER is considered to be robust because the

The extrapolation of the experimentally measured energy confinement time in existing tokamaks towards ITER is considered to be robust because the Report from the lecture presented by Robert Aymar Report written by Michael Tendler, Alfvén Laboratory, Royal Institute of Technology, Stockholm, Sweden At the time of the meeting, we were once again at

More information

Simple examples of MHD equilibria

Simple examples of MHD equilibria Department of Physics Seminar. grade: Nuclear engineering Simple examples of MHD equilibria Author: Ingrid Vavtar Mentor: prof. ddr. Tomaž Gyergyek Ljubljana, 017 Summary: In this seminar paper I will

More information

EF2200 Plasma Physics: Fusion plasma physics

EF2200 Plasma Physics: Fusion plasma physics EF2200 Plasma Physics: Fusion plasma physics Guest lecturer: Thomas Jonsson, johnso@kth.se Department for Fusion Plasma Physics School of Electrical Engineering 1 ITER (EU, China, India, Japan, Russia,

More information

Denis Bytschkow. Investigation of MHD mode rotation in the tokamak ASDEX Upgrade

Denis Bytschkow. Investigation of MHD mode rotation in the tokamak ASDEX Upgrade Denis Bytschkow Investigation of MHD mode rotation in the tokamak ASDEX Upgrade IPP 1/341 September, 2010 P H Y S I K - D E P A R T M E N T TECHNISCHE UNIVERSITÄT MÜNCHEN Investigation of MHD mode rotation

More information

Issues for Neutron Calculations for ITER Fusion Reactor

Issues for Neutron Calculations for ITER Fusion Reactor Introduction Issues for Neutron Calculations for ITER Fusion Reactor Erik Nonbøl and Bent Lauritzen Risø DTU, National Laboratory for Sustainable Energy Roskilde, Denmark Outline 1. Fusion development

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

22.615, MHD Theory of Fusion Systems Prof. Freidberg Lecture 15: Alternate Concepts (with Darren Sarmer)

22.615, MHD Theory of Fusion Systems Prof. Freidberg Lecture 15: Alternate Concepts (with Darren Sarmer) 22.615, MHD Theory of Fusion Systems Prof. Freidberg Lecture 15: Alternate Concepts (with Darren Sarmer) 1. In todays lecture we discuss the basic ideas behind the main alternate concepts to the tokamak.

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

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

Principles of Nuclear Fusion & Fusion research in Belgium R. R. Weynants

Principles of Nuclear Fusion & Fusion research in Belgium R. R. Weynants Principles of Nuclear Fusion & Fusion research in Belgium R. R. Weynants Laboratorium voor Plasmafysica - Laboratoire de Physique des Plasmas Koninklijke Militaire School - Ecole Royale Militaire 1040

More information

ª 10 KeV. In 2XIIB and the tandem mirrors built to date, in which the plug radius R p. ª r Li

ª 10 KeV. In 2XIIB and the tandem mirrors built to date, in which the plug radius R p. ª r Li Axisymmetric Tandem Mirrors: Stabilization and Confinement Studies R. F. Post, T. K. Fowler*, R. Bulmer, J. Byers, D. Hua, L. Tung Lawrence Livermore National Laboratory *Consultant, Presenter This talk

More information

Electron Bernstein Wave Heating in the TCV Tokamak

Electron Bernstein Wave Heating in the TCV Tokamak Electron Bernstein Wave Heating in the TCV Tokamak A. Mueck 1, Y. Camenen 1, S. Coda 1, L. Curchod 1, T.P. Goodman 1, H.P. Laqua 2, A. Pochelon 1, TCV Team 1 1 Ecole Polytechnique Fédérale de Lausanne

More information

Recent Developments and Applications of Bayesian Data Analysis in Fusion Science: Integrated Data Analysis

Recent Developments and Applications of Bayesian Data Analysis in Fusion Science: Integrated Data Analysis MPI for Extraterrestrial Physics: Bayes Forum Recent Developments and Applications of Bayesian Data Analysis in Fusion Science: Integrated Data Analysis R. Fischer, L. Barrera, A. Burckhart, M.G. Dunne,

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

Exploration of Configurational Space for Quasi-isodynamic Stellarators with Poloidally Closed Contours of the Magnetic Field Strength

Exploration of Configurational Space for Quasi-isodynamic Stellarators with Poloidally Closed Contours of the Magnetic Field Strength Exploration of Configurational Space for Quasi-isodynamic Stellarators with Poloidally Closed Contours of the Magnetic Field Strength V.R. Bovshuk 1, W.A. Cooper 2, M.I. Mikhailov 1, J. Nührenberg 3, V.D.

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

NIMEQ: MHD Equilibrium Solver for NIMROD

NIMEQ: MHD Equilibrium Solver for NIMROD NIMEQ: MHD Equilibrium Solver for NIMOD E.C.Howell, C..Sovinec University of Wisconsin-Madison 5 th Annual Meeting of Division of Plasma Physics Dallas, Texas, Nov. 17-Nov. 1,8 1 Abstract A Grad-Shafranov

More information

MHD-particle simulations and collective alpha-particle transport: analysis of ITER scenarios and perspectives for integrated modelling

MHD-particle simulations and collective alpha-particle transport: analysis of ITER scenarios and perspectives for integrated modelling MHD-particle simulations and collective alpha-particle transport: analysis of ITER scenarios and perspectives for integrated modelling G. Vlad, S. Briguglio, G. Fogaccia, F. Zonca Associazione Euratom-ENEA

More information

Experimental Investigations of Magnetic Reconnection. J Egedal. MIT, PSFC, Cambridge, MA

Experimental 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 information

Plasma geometry and current profile identification on ASDEX Upgrade using an integrated equilibrium generation and interpretation system.

Plasma geometry and current profile identification on ASDEX Upgrade using an integrated equilibrium generation and interpretation system. TH/P3-7 Plasma geometry and current profile identification on ASDEX Upgrade using an integrated equilibrium generation and interpretation system. P.J. Mc Carthy 1, C.B. Forest 2, M. Foley 1, L.Giannone

More information

Turbulence in Tokamak Plasmas

Turbulence in Tokamak Plasmas ASDEX Upgrade Turbulence in Tokamak Plasmas basic properties and typical results B. Scott Max Planck Institut für Plasmaphysik Euratom Association D-85748 Garching, Germany Uni Innsbruck, Nov 2011 Basics

More information

Numerical calculation of the Hamada basis vectors for three-dimensional toroidal magnetic configurations

Numerical calculation of the Hamada basis vectors for three-dimensional toroidal magnetic configurations PHYSICS OF PLASMAS 12, 072513 2005 Numerical calculation of the Hamada basis vectors for three-dimensional toroidal magnetic configurations J. N. Talmadge and S. P. Gerhardt a HSX Plasma Laboratory, University

More information

On the physics of shear flows in 3D geometry

On the physics of shear flows in 3D geometry On the physics of shear flows in 3D geometry C. Hidalgo and M.A. Pedrosa Laboratorio Nacional de Fusión, EURATOM-CIEMAT, Madrid, Spain Recent experiments have shown the importance of multi-scale (long-range)

More information

Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power

Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power Compact, spheromak-based pilot plants for the demonstration of net-gain fusion power Derek Sutherland HIT-SI Research Group University of Washington July 25, 2017 D.A. Sutherland -- EPR 2017, Vancouver,

More information

MHD. Jeff Freidberg MIT

MHD. Jeff Freidberg MIT MHD Jeff Freidberg MIT 1 What is MHD MHD stands for magnetohydrodynamics MHD is a simple, self-consistent fluid description of a fusion plasma Its main application involves the macroscopic equilibrium

More information

Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas

Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas Edge Rotational Shear Requirements for the Edge Harmonic Oscillation in DIII D Quiescent H mode Plasmas by T.M. Wilks 1 with A. Garofalo 2, K.H. Burrell 2, Xi. Chen 2, P.H. Diamond 3, Z.B. Guo 3, X. Xu

More information

The Levitated Dipole Experiment: Towards Fusion Without Tritium

The Levitated Dipole Experiment: Towards Fusion Without Tritium The Levitated Dipole Experiment: Towards Fusion Without Tritium Jay Kesner MIT M.S. Davis, J.E. Ellsworth, D.T. Garnier, M.E. Mauel, P.C. Michael, P.P. Woskov MCP I3.110 Presented at the EPS Meeting, Dublin,

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

TRANSPORT PROGRAM C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER

TRANSPORT PROGRAM C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER TRANSPORT PROGRAM C-Mod C-MOD 5 YEAR REVIEW MAY, 2003 PRESENTED BY MARTIN GREENWALD MIT PLASMA SCIENCE & FUSION CENTER C-MOD - OPPORTUNITIES AND CHALLENGES Prediction and control are the ultimate goals

More information

Plasma spectroscopy when there is magnetic reconnection associated with Rayleigh-Taylor instability in the Caltech spheromak jet experiment

Plasma spectroscopy when there is magnetic reconnection associated with Rayleigh-Taylor instability in the Caltech spheromak jet experiment Plasma spectroscopy when there is magnetic reconnection associated with Rayleigh-Taylor instability in the Caltech spheromak jet experiment KB Chai Korea Atomic Energy Research Institute/Caltech Paul M.

More information

The fast-ion distribution function

The fast-ion distribution function The fast-ion distribution function Source Collisions Orbits RF Losses W. Heidbrink 3 MeV & 14.7 MeV protons Charge Exchange Reactivity σv Complex neutral beam sources are described by a few parameters

More information

Physics and Operations Plan for LDX

Physics and Operations Plan for LDX Physics and Operations Plan for LDX Columbia University A. Hansen D.T. Garnier, M.E. Mauel, T. Sunn Pedersen, E. Ortiz Columbia University J. Kesner, C.M. Jones, I. Karim, P. Michael, J. Minervini, A.

More information

Prospects of Nuclear Fusion Energy Research in Lebanon and the Middle-East

Prospects of Nuclear Fusion Energy Research in Lebanon and the Middle-East Prospects of Nuclear Fusion Energy Research in Lebanon and the Middle-East Ghassan Antar Physics Department American University of Beirut http://www.aub.edu.lb/physics/lpfd Outline 1. Introduction and

More information

PHYSICS BASIS FOR THE GASDYNAMIC MIRROR (GDM) FUSION ROCKET. Abstract

PHYSICS BASIS FOR THE GASDYNAMIC MIRROR (GDM) FUSION ROCKET. Abstract PHYSICS BASIS FOR THE GASDYNAMIC MIRROR (GDM) FUSION ROCKET T. Kammash Department of Nuclear Engineering and Radiological Sciences University of Michigan Ann Arbor, MI 48109 (313) 764-0205 W. Emrich Jr.

More information

Plasma instabilities. Dr Ben Dudson, University of York 1 / 37

Plasma instabilities. Dr Ben Dudson, University of York 1 / 37 Plasma instabilities Dr Ben Dudson, University of York 1 / 37 Previously... Plasma configurations and equilibrium Linear machines, and Stellarators Ideal MHD and the Grad-Shafranov equation Collisional

More information

Role and Challenges of Fusion Nuclear Science and Technology (FNST) toward DEMO

Role and Challenges of Fusion Nuclear Science and Technology (FNST) toward DEMO Role and Challenges of Fusion Nuclear Science and Technology (FNST) toward DEMO Mohamed Abdou Distinguished Professor of Engineering and Applied Science (UCLA) Director, Center for Energy Science & Technology

More information

MHD Modes of Solar Plasma Structures

MHD Modes of Solar Plasma Structures PX420 Solar MHD 2013-2014 MHD Modes of Solar Plasma Structures Centre for Fusion, Space & Astrophysics Wave and oscillatory processes in the solar corona: Possible relevance to coronal heating and solar

More information

Progress of Confinement Physics Study in Compact Helical System

Progress of Confinement Physics Study in Compact Helical System 1st IAEA Fusion Energy Conference Chengdu, China, 16-1 October, 6 IAEA-CN-149/ EX/5-5Rb Progress of Confinement Physics Study in Compact Helical System S. Okamura et al. NIFS-839 Oct. 6 1 EX/5-5Rb Progress

More information

References and Figures from: - Basdevant, Fundamentals in Nuclear Physics

References and Figures from: - Basdevant, Fundamentals in Nuclear Physics Lecture 22 Fusion Experimental Nuclear Physics PHYS 741 heeger@wisc.edu References and Figures from: - Basdevant, Fundamentals in Nuclear Physics 1 Reading for Next Week Phys. Rev. D 57, 3873-3889 (1998)

More information

Effect of ideal kink instabilities on particle redistribution

Effect of ideal kink instabilities on particle redistribution Effect of ideal kink instabilities on particle redistribution H. E. Ferrari1,2,R. Farengo1, P. L. Garcia-Martinez2, M.-C. Firpo3, A. F. Lifschitz4 1 Comisión Nacional de Energía Atómica, Centro Atomico

More information

purposes is highly encouraged.

purposes is highly encouraged. The following slide show is a compilation of slides from many previous similar slide shows that have been produced by different members of the fusion and plasma physics education community. We realize

More information

Experimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related to Indian Test Blanket Module for ITER

Experimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related to Indian Test Blanket Module for ITER Experimental Facility to Study MHD effects at Very High Hartmann and Interaction parameters related to Indian Test Blanket Module for ITER P. Satyamurthy Bhabha Atomic Research Centre, India P. Satyamurthy,

More information

Effect of ExB Driven Transport on the Deposition of Carbon in the Outer Divertor of. ASDEX Upgrade

Effect of ExB Driven Transport on the Deposition of Carbon in the Outer Divertor of. ASDEX Upgrade Association Euratom-Tekes ASDEX Upgrade Effect of ExB Driven Transport on the Deposition of Carbon in the Outer Divertor of ASDEX Upgrade L. Aho-Mantila 1,2, M. Wischmeier 3, K. Krieger 3, V. Rohde 3,

More information

A.G. PEETERS UNIVERSITY OF BAYREUTH

A.G. PEETERS UNIVERSITY OF BAYREUTH IN MEMORIAM GRIGORY PEREVERZEV A.G. PEETERS UNIVERSITY OF BAYREUTH ESF Workshop (Garching 2013) Research areas Grigory Pereverzev. Current drive in magnetized plasmas Transport (ASTRA transport code) Wave

More information

Finite-Orbit-Width Effect and the Radial Electric Field in Neoclassical Transport Phenomena

Finite-Orbit-Width Effect and the Radial Electric Field in Neoclassical Transport Phenomena 1 TH/P2-18 Finite-Orbit-Width Effect and the Radial Electric Field in Neoclassical Transport Phenomena S. Satake 1), M. Okamoto 1), N. Nakajima 1), H. Sugama 1), M. Yokoyama 1), and C. D. Beidler 2) 1)

More information

Issues of Perpendicular Conductivity and Electric Fields in Fusion Devices

Issues of Perpendicular Conductivity and Electric Fields in Fusion Devices Issues of Perpendicular Conductivity and Electric Fields in Fusion Devices Michael Tendler, Alfven Laboratory, Royal Institute of Technology, Stockholm, Sweden Plasma Turbulence Turbulence can be regarded

More information

Integrated equilibrium reconstruction and MHD stability analysis of tokamak plasmas in the EU-IM platform

Integrated equilibrium reconstruction and MHD stability analysis of tokamak plasmas in the EU-IM platform EUROFUSION WPCD-PR(16) 15379 R Coelho et al. Integrated equilibrium reconstruction and MHD stability analysis of tokamak plasmas in the EU-IM platform Preprint of Paper to be submitted for publication

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

Tokamak Fusion Basics and the MHD Equations

Tokamak Fusion Basics and the MHD Equations MHD Simulations for Fusion Applications Lecture 1 Tokamak Fusion Basics and the MHD Equations Stephen C. Jardin Princeton Plasma Physics Laboratory CEMRACS 1 Marseille, France July 19, 21 1 Fusion Powers

More information

Runaway electron losses enhanced by resonant magnetic perturbations

Runaway electron losses enhanced by resonant magnetic perturbations Runaway electron losses enhanced by resonant magnetic perturbations G. Papp 1,2, M. Drevlak 3, T. Fülöp 1, P. Helander 3, G. I. Pokol 2 1) Chalmers University of Technology, Göteborg, Sweden 2) Budapest

More information

Unpressurized steam reactor. Controlled Fission Reactors. The Moderator. Global energy production 2000

Unpressurized steam reactor. Controlled Fission Reactors. The Moderator. Global energy production 2000 From last time Fission of heavy elements produces energy Only works with 235 U, 239 Pu Fission initiated by neutron absorption. Fission products are two lighter nuclei, plus individual neutrons. These

More information

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

DIAGNOSTICS 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 information

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

Direct 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 information

Sensors Plasma Diagnostics

Sensors Plasma Diagnostics Sensors Plasma Diagnostics Ken Gentle Physics Department Kenneth Gentle RLM 12.330 k.gentle@mail.utexas.edu NRL Formulary MIT Formulary www.psfc.mit.edu/library1/catalog/ reports/2010/11rr/11rr013/11rr013_full.pdf

More information

The 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

The 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 information

Progressing Performance Tokamak Core Physics. Marco Wischmeier Max-Planck-Institut für Plasmaphysik Garching marco.wischmeier at ipp.mpg.

Progressing Performance Tokamak Core Physics. Marco Wischmeier Max-Planck-Institut für Plasmaphysik Garching marco.wischmeier at ipp.mpg. Progressing Performance Tokamak Core Physics Marco Wischmeier Max-Planck-Institut für Plasmaphysik 85748 Garching marco.wischmeier at ipp.mpg.de Joint ICTP-IAEA College on Advanced Plasma Physics, Triest,

More information