The Future of Boundary Plasma and Material Science

Save this PDF as:
 WORD  PNG  TXT  JPG

Size: px
Start display at page:

Download "The Future of Boundary Plasma and Material Science"

Transcription

1 The Future of Boundary Plasma and Material Science Dennis Whyte Plasma Science & Fusion Center, MIT, Cambridge USA Director, Plasma Surface Interaction Science Center (psisc.org) APS Sherwood Meeting of Fusion Theory Atlanta, April

2 Outline Defining the Challenge for Fusion Energy Boundaries The Multiscale Science of Plasma-Material Interactions Ø Processes, measurement and exposure Developing a dimensionless parameter wind-tunnel for fusion PMI Critical needs for boundary plasma understanding & prediction. 2

3 Outline Defining the Challenge for Fusion Energy Boundaries COMMENTS The Multiscale Science of Plasma-Material Interactions - Ø Boundary/PMI Processes, measurement science and exposure is too broad to be inclusive of every topic of interest Developing a dimensionless parameter wind-tunnel for fusion PMI - The following comments reflect my personal views on critical paths forward in both experiment, theory and computation Critical needs for boundary plasma understanding & prediction. 3

4 Outline Defining the Challenge for Fusion Energy Boundaries The Multiscale Science of Plasma-Material Interactions Ø Processes, measurement and exposure Developing a dimensionless parameter wind-tunnel for fusion PMI Critical needs for boundary plasma understanding & prediction. 4

5 Demo constants: T > 1000K, P heat /S ~ 1 MW/m 2 for 30,000,000 seconds. ITER falls far short ITER ARIES-AT ARIES-CS ARIES-ST Duration (s) 400 3x10 7 3x10 7 3x10 7 Ambient T (K) R (m) R/a P fusion / S (MW/m 2 ) ~ P/S (MW/m 2 ) P/A div (MW/m 2 ) >20 20 A divertor / S ~ 5-10% 5

6 Boundary/PMI Science Gap to FNSF/ Reactors is More like a 3-D Chasm 6

7 Boundary/PMI Science Gap to FNSF/ Reactors is More like a 3-D Chasm Why these axes? 7

8 The PMI Science Challenge & Fusion Viability are inextricably linked Fusion Viability 1. Average neutron power loading ~ 4 MW/m 2 PSI Challenge 1. Global average exhaust power P/S ~ 1 MW/m 2 8

9 PFCs must be thin (~5 mm) to satisfy heat exhaust but thick to resist erosion & material removal & Continually maintain conformability to B field Steady-state 10 MW/m 2 heat exhaust pushes high- T He gas cooling to limits, no allowance for transients. Small Transient heat loading limits lifetime of even best materials While loss of conforming surface to B greatly accelerates loss of PFC viability & severe plasma effects. 9

10 The PMI Science Challenge & Fusion Viability are inextricably linked Fusion Viability 1. Average neutron power loading ~ 4 MW/m 2 2. Continuous 24/7 power production. PSI Challenge 1. Global average exhaust power P/S ~ 1 MW/m 2 2. Global energy throughput > 30 TJ/m 2 delivered by plasma 10

11 Erosion limits are set by complex PMI interplay & total energy throughput: Extrapolation from present devices to FNSF/reactors at least x10,000 Tungsten main-wall: ~1-10 tons of erosion from charge-exchange neutrals 300 s 2,000 s 4,300 s 9,000 s 22,000 s The wall surface never truly equilibrates because erosion cannot be turned off at all surfaces. 11

12 Material limits set by complex PMI & total energy throughput: Extrapolation from present devices to FSNF/reactors at least x10, s 2,000 s 4,300 s 9,000 s Example of 10 micron W surface microstructure over ~1/4 day in PISCES lab plasma at 1100 K Baldwin et al PSI ,000 s Micron deep W fuzz grown in Alcator C-Mod divertor in ~10 seconds at 1500 K! Wright et al NF

13 The PMI Science Challenge & Fusion Viability are inextricably linked Fusion Viability 1. Average neutron power loading ~ 4 MW/m 2 2. Continuous 24/7 power production. 3. Thermodynamics demand high ambient temperature. PSI Challenge 1. Global average exhaust power P/S ~ 1 MW/m 2 2. Global energy throughput > 30 TJ/m 2 delivered by plasma 3. Fundamental new regime of physical chemistry for plasmafacing materials. 13

14 Required High-T walls present a fundamentally new regime of physical chemistry for PMI science that has not even been approached in an integrated manner Arrenhius equation Rates exp exp E o T material 11,600K ( )K 14

15 Example from PISCES test-stand: Nano- fuzz highly T dependent 900 K Tungsten surface after exposure to ~1 hour Helium plasma K 1320 K Baldwin et al PSI

16 Outline Defining the Challenge for Fusion Energy Boundaries The Multiscale Science of Plasma-Material Interactions Ø Processes, measurement and exposure Developing a dimensionless parameter wind-tunnel for fusion PMI Critical needs for boundary plasma understanding & prediction. 16

17 The plasma-surface interface is perturbing & complex e.g. the divertor surface is reconstituted ~100 times per second Simplified Surface Picture + ordered crystal sputtered imurity atom mm surface nm Realistic Surface Picture + Long-range Ion impact Material Recycling Fuel Recycling material transport chemical removal secondary electron reflection emission implantation sputteringte ionization γ excitation + redeposition chargeexchange + ionization + dissociation recombination sheath potential - fuel codeposition surface fuel saturation fuel diffusion & permeation fuel trapping at defects vacancy/void defects from ion and neutron radiation bubbles & blisters amorphous film growth Electron + H/D/T fuel ion + PFC material ion H/D/T fuel neutral atom PFC material atom Redeposited PFC material atom Wirth, Whyte, et al MRS

18 PMI/Boundary plasmas in a confinement device set by coupled, multi-scale processes 18

19 The Core of Multi-scale PMI Science is Hyper-Sensitive to Material Temperature Arrenhius rates Rates exp exp E o T material 11,600K ( )K 19

20 The Plasma-Surface Interaction Science Center: addressing multiscale diagnosis 20

21 The Plasma-Surface Interaction Science Center: addressing multiscale modeling & simulation 21

22 We seriously think we can figure out this mess by measuring surfaces every year or so in tokamaks?* * What we do now 22

23 AGNOSTIC: Proof-of-principle diagnostic development on Alcator C-Mod to provide first shot-to-shot diagnosis of plasma-facing surfaces (4) Advanced in-vessel neutron and gamma spectroscopy, unoflred with GEANT4, maps all surface properties (depth resolved!)" Hartwig, et al, Rev. Sci. Instrum

24 AGNOSTIC* requires leading edge nuclear transport modeling and simulations Full 3-D model of tokamak GEANT4 simulation of Scintillation detection *Accelerator-based Gamma and Neutron Observing Surface-diagnosing Tool for In-situ Components 24

25 Example: Complete synthetic diagnostic of Boron film thickness in Alcator C-Mod 25

26 Outline Defining the Challenge for Fusion Energy Boundaries The Multiscale Science of Plasma-Material Interactions Ø Processes, measurement and exposure Developing a dimensionless parameter wind-tunnel for fusion PMI Critical needs for boundary plasma understanding & prediction. 26

27 Proposal: Use dimensionless similarity to study coupled issues of edge plasma, PMI and materials in a scaled-down device* Dimensionless parameter scaling techniques are a powerful tool to study complex physical systems (e.g. wind-tunnel for aeronautics) Ø Especially in tokamak fusion experiments where full-size cost is prohibitive. Objective: provide similarity for critical parameters in reactor while avoiding technology limits in scaled-down device Ø Full similarity is not possible Ø The well-known P/R divertor scaling does not meet these objectives A new P/S scaling (actually a set of requirements) provides fidelity to reactor divertor conditions in a small device which is used as the physics basis for Vulcan. * Special Issue on the Vulcan Conceptual Design, Fusion Engineering Design March

28 Lessons about using dimensionless similarity in core Critical dimensionless parameters are posited based on physical reasoning (without proof), for example Kadomtsev constants M i M p ~ a R q ~ B T B P β ~ nt B 2 ν * ~ nr ρ * ~ T 1/2 T 2 BR Leads to size scaling of plasma parameters n ~ R 2 T ~ R 1/2 B ~ R 5/4 28

29 Lessons about using dimensionless similarity in core Critical dimensionless parameters are posited based on physical reasoning (without proof), for example Kadomtsev constants M i M p ~ a R q ~ B T B P β ~ nt B 2 ν * ~ nr ρ * ~ T 1/2 T 2 BR Leads to size scaling of plasma parameters n ~ R 2 T ~ R 1/2 B ~ R 5/4 But now the reality of the scaling effort must be accounted 1) Magnetic field B has a hard technology limit at fixed aspect ratio 2) Reactor must max. B since power density ~ B 4 Therefore full matching is not practically useful: what to relax? One chooses rho* based on physical reasoning Far below unity and therefore avoids any threshold effect. Is practically difficult to vary in one device. N.B.: this practical strategy leads to experimental validation* * Luce et al PPCF 50 (2008) 29

30 The challenge is that many more parameters become important in boundary / PMI. Cleverness in similarity is mandatory Lackner and others (90 s) made reasonable argument that atomic physics important in SOL: posited T/E atomic =cst. à T = cst. Global power balance // Spitzer conduction // Pressure balance P/R scaling Much is implicit in P/R scaling! Radial power width λ r ~ R, which requires q // ~ 1/R!! This guarantees cannot implement P/R scaling in a scaled-down device since power density must be near technology limit ~10 MW/m 2 Aspect ratio must be matched (ST does not simulate AT reactor) Density must be much larger in smaller device (current drive)? Lackner, Cont. Plasma Physics 15 (1994), Whyte, et al Fus. Eng. Des. (2012) 30

31 The challenge is that many more parameters become important in boundary / PMI. Cleverness in similarity is mandatory Lackner and others (90 s) made reasonable argument that atomic physics important in SOL: posited T/E atomic =cst. à T = cst. Global power balance // Spitzer conduction // Pressure balance P/R scaling N.B. much implicit in P/R scaling! Radial power width λ r ~ R, which requires q // ~ R -1!! This guarantees cannot implement P/R scaling in a scaled-down device since power density must be near technology max. ~ GW/m 2 in reactor Not practical Aspect ratio must be matched (ST does not simulate AT reactor) Density must be much larger in smaller device (current drive)? 31

32 Basic argument: If atomic physics is important in boundary plasma then surely PMI is too! Which dimensionless parameters? 32

33 Basic argument: If atomic physics is important in boundary plasma then surely PMI is too! Material removal through sputtering E D+ E B ~ T e E B Y phys ~ f ( T e E B, M D M W ) Y chem ~ f ( T e E B, M D M W, T W E B ) 33

34 Basic argument: If atomic physics is important in boundary plasma then surely PMI is too! Electrostatic redeposition ( λ MFP ~ M E W W ) 1/2 n e S W λ MFP ~ E 1/2 W M 1/2 W n 1/2 e T 1/2 1 e S W L Debye λ MFP L Presheath ~ λ MFP ρ H + ~ B E 1/2 W M 1/2 W n 1 e T 1/2 1 e S W 34

35 Basic argument: If atomic physics is important in boundary plasma then surely PMI is too! Gyro-orbit redeposition λ MFP ρ W + ~ B M 1 W n 1 1 e S W Reactor divertor n ~ m -3 T ~ 10 ev B ~ 6 T One surface atom can theoretically undergo ~billion of these cycles in one year. 35

36 PMI figures of merit in reactor à Must match divertor n, T, B in scaled down device to avoid thresholds in figures of merit à But relaxed divertor collisionality OK Vulcan Special Issue FED

37 Basic argument: If atomic physics is important in boundary plasma then surely PMI is too! Plasma & ambient T à material physics T W E W ~ n T 3/2 B B δ W κ W + T ambient σ Thermal σ Yield ~ n T 3/2 B B δ W R W D H in W exp E W, H T W 37

38 Basic argument: If atomic physics is important in boundary plasma then surely PMI is too! Plasma & ambient T à material physics TW 3/2 B δ W ~nt + Tambient EW B κw σ Thermal 3/2 B δ W ~nt σ Yield B RW DH in W EW, H exp TW 38

39 Material physics figures of merit in reactor à Must match divertor n, T, B AND ambient temperature in scaled down device Vulcan Special Issue FED

40 Proposed P/S scaling rules provide matched divertor/ SOL parameters in scaled-down device à reactor PMI wind-tunnel VULCAN 1. Non-inductive steady-state operation (arbitrary long pulses) 2. Areal heating power density P/S (~1 MW/m 2 ) 3. Magnetic field B (~6-7 Tesla) of reactor { λ p ~ R through ballooning limit} 4. Geometry matched: R/a, q, L // /R, etc. 5. Core density: n ~ R -2/7 6. Ambient wall temperature matched (> 500 C) With an implicit 7 th requirement that embodies the philosophy of the scaling law: 7. The scaling laws must actually allow for the construction and operation of the scaled down device (duh!) 40

41 P/S scaling : A practical approach to providing a high fidelity reactor PMI wind-tunnel P/R inherently fails to match atomic physics (n~r -1 ) & cannot be operated due to violation of heat flux limits 41

42 Vulcan design scope: R=1.2 m, P LHCD ~20 MW Vulcan Special Issue FED

43 Double-can vacuum vessel: High Temperature wall Points here 43

44 And the MOST important material in magnetic fusion? 44

45 And the MOST important material in magnetic fusion? The MAGNET! Points here YBCO high-t superconductors coils could revolutionize magnetic fusion by up to x2 increase in B 45

46 YBCO Superconductor tapes à Demountable SC coils à Vertical lift-off maintenance Points here 46

47 YBCO Superconductor tapes à Demountable SC coils à Vertical lift-off maintenance Points here 47

48 Double-can vacuum vessel: High T-wall + eliminate sector maintenance Points here 48

49 Double-can vacuum vessel: High T-wall + eliminate sector maintenance Points here 49

50 VULCAN The 24/7 PMI wind-tunnel p.s. we should design ST and stellarator versions too! Points here Vulcan Special Issue FED

51 Vulcan addresses the PMI chasms to FNSF/reactors 51

52 The US and world will lose its first glimpse of a reactor divertor environment with the C-Mod termination on the eve of the hot W divertor Comments Bulk tungsten outer divertor from room temperature à 600 C /w reactor-like P/S, n e, T e, B Innovative divertor design: toroidally continuous aligned W surfaces à 0.5 degree grazing incidence à can actually exploit high flux expansion vertical or snowflake topology 52

53 Outline Defining the Challenge for Fusion Energy Boundaries The Multiscale Science of Plasma-Material Interactions Ø Processes, measurement and exposure Developing a dimensionless parameter wind-tunnel for fusion PMI Critical needs for boundary plasma understanding & prediction. 53

54 We desperately need coherent data and a validated model for the SOL width Recent experiments across US devices indicates width only depends on poloidal field à 1 mm widths in ITER (like C- Mod) λ SOL ~ a I p ~ 1 B p Makowski, et al APS

55 We desperately need coherent data and a validated model for the SOL width Recent experiments across US devices indicates width only depends on poloidal field à 1 mm widths in ITER (like C- Mod) Yet the separatrix pressure is well constrained Ø Pedestal stability: p sep ~ 5% p ped Ø Power exhaust: P ~ λ SOL p sep T 1/2 55

56 We desperately need cohesive data and a validated model for the SOL width Recent experiments across US devices indicates width only depends on poloidal field à 1 mm widths in ITER (like C- Mod) Yet the separatrix pressure is well constrained Ø Pedestal stability: p sep ~ 5% p ped Ø Power exhaust: P ~ λ SOL p sep T 1/2 A 1 mm SOL width in ITER would require a separatrix pressure equal to that at the top of the pedestal?? 56

57 The inevitable x2-3 increase in areal energy density from ITER à reactor will disallow any significant instability W th A wall τ 1/ 2 ~ pv A(R /c s ) ~ P 1/ 2 1/ 2 fusion ε R 1/ 2 ARIES-AT ARIES-ST Limit ARIES-RS Material thermal limits Material T max (K) Limit MJ m -2 s -1/2 Be C W ITER 30 mm 57

58 ELMs will not be allowed à ELMy H-mode is not a reactor relevant confinement regime à extremely high priority to develop intrinsically ELM-free pedestals (QH, I-mode) Tungsten Before exposure W th pv 1/ 2 1/ 2 ~ ~ P ε R fusion Awall τ 1/ 2 A(R /c s )1/ 2 ARIES-AT Limit After 5 large ELMs ARIES-ST ARIES-RS ITER 30 mm ~30 MJ/m2/s1/2 58

59 ELMs will not be allowed à ELMy H-mode is not a reactor relevant confinement regime à Extremely high priority to develop intrinsically ELM-free pedestals (QH, I-mode) Tungsten Before exposure After 5 large ELMs ~30 MJ/m2/s1/2 59

60 Magnetic Fusion Plasma Design Design issues from core à edge Report Card Experimental Demonstration Validated Predictive Theory/Simulation Core pressure/kink limits Current drive and bootstrap Pedestal stability boundary Self-regulated pedestal w/o ELMs X SOL heat width? X Divertor T and heat flux below limits X PMI & PFC T > 500 C X X Erosion / redeposition control for 30,000,000 seconds + 20 dpa X X 60

61 Take away messages The boundary plasma and its material interface will continue to grow in importance and challenges for integrated fusion devices à reactor This is not simply a technology issue, there is no unobtainium, rather we must push ourselves to the knowledge frontiers of boundary plasma and material science. Fusion theory and computation must become more than plasma theory and will be critical in achieving success. 61

62 Extra Comments 62

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices

Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices Comparison of tungsten fuzz growth in Alcator C-Mod and linear plasma devices G.M. Wright 1, D. Brunner 1, M.J. Baldwin 2, K. Bystrov 3, R. Doerner 2, B. LaBombard 1, B. Lipschultz 1, G. de Temmerman 3,

More information

Tokamak 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 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 information

Overview of Pilot Plant Studies

Overview of Pilot Plant Studies Overview of Pilot Plant Studies and contributions to FNST Jon Menard, Rich Hawryluk, Hutch Neilson, Stewart Prager, Mike Zarnstorff Princeton Plasma Physics Laboratory Fusion Nuclear Science and Technology

More information

Fusion Nuclear Science - Pathway Assessment

Fusion Nuclear Science - Pathway Assessment Fusion Nuclear Science - Pathway Assessment C. Kessel, PPPL ARIES Project Meeting, Bethesda, MD July 29, 2010 Basic Flow of FNS-Pathways Assessment 1. Determination of DEMO/power plant parameters and requirements,

More information

Innovative fabrication method of superconducting magnets using high T c superconductors with joints

Innovative fabrication method of superconducting magnets using high T c superconductors with joints Innovative fabrication method of superconducting magnets using high T c superconductors with joints (for huge and/or complicated coils) Nagato YANAGI LHD & FFHR Group National Institute for Fusion Science,

More information

A SUPERCONDUCTING TOKAMAK FUSION TRANSMUTATION OF WASTE REACTOR

A 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 information

Fusion Nuclear Science (FNS) Mission & High Priority Research

Fusion Nuclear Science (FNS) Mission & High Priority Research Fusion Nuclear Science (FNS) Mission & High Priority Research Topics Martin Peng, Aaron Sontag, Steffi Diem, John Canik, HM Park, M. Murakami, PJ Fogarty, Mike Cole ORNL 15 th International Spherical Torus

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

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

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

More information

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

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

More information

This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under contract

This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under contract This work was performed under the auspices of the U.S. Department of Energy by under contract DE-AC52-7NA27344. Lawrence Livermore National Security, LLC The ITER tokamak Tungsten (W) is attractive as

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

A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS

A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS A THEORETICAL AND EXPERIMENTAL INVESTIGATION INTO ENERGY TRANSPORT IN HIGH TEMPERATURE TOKAMAK PLASMAS Presented by D.P. SCHISSEL Presented to APS Centennial Meeting March 20 26, 1999 Atlanta, Georgia

More information

Physics basis for similarity experiments on power exhaust between JET and ASDEX Upgrade with tungsten divertors

Physics basis for similarity experiments on power exhaust between JET and ASDEX Upgrade with tungsten divertors Physics basis for similarity experiments on power exhaust between JET and ASDEX Upgrade with tungsten divertors S. Wiesen, T. Eich, M. Bernert, S. Brezinsek, C. Giroud, E. Joffrin, A. Kallenbach, C. Lowry,

More information

Progress in characterization of the H-mode pedestal

Progress in characterization of the H-mode pedestal Journal of Physics: Conference Series Progress in characterization of the H-mode pedestal To cite this article: A W Leonard 2008 J. Phys.: Conf. Ser. 123 012001 View the article online for updates and

More information

C-Mod Core Transport Program. Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center

C-Mod Core Transport Program. Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center C-Mod Core Transport Program Presented by Martin Greenwald C-Mod PAC Feb. 6-8, 2008 MIT Plasma Science & Fusion Center Practical Motivations for Transport Research Overall plasma behavior must be robustly

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

Demountable Superconducting Magnet Coils

Demountable Superconducting Magnet Coils FESAC TEC Report 1 Demountable Superconducting Magnet Coils A strategic technology to address key nuclear materials, construction, and maintenance issues Brandon Sorbom, Bob Mumgaard, Joseph Minervini,

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

The role of PMI in MFE/IFE common research

The role of PMI in MFE/IFE common research The role of PMI in MFE/IFE common research Presented by Doerner for the Team and TITAN 1-1 Participants In 2006, Jupiter II recognized that PMI was a bridge issue between MFE and IFE R&D Both MFE and IFE

More information

Erosion/redeposition analysis of CMOD Molybdenum divertor and NSTX Liquid Lithium Divertor

Erosion/redeposition analysis of CMOD Molybdenum divertor and NSTX Liquid Lithium Divertor Erosion/redeposition analysis of CMOD Molybdenum divertor and NSTX Liquid Lithium Divertor J.N. Brooks, J.P. Allain Purdue University PFC Meeting MIT, July 8-10, 2009 CMOD Mo tile divertor erosion/redeposition

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

Analysis 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 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 information

Physics of the detached radiative divertor regime in DIII-D

Physics of the detached radiative divertor regime in DIII-D Plasma Phys. Control. Fusion 41 (1999) A345 A355. Printed in the UK PII: S741-3335(99)97299-8 Physics of the detached radiative divertor regime in DIII-D M E Fenstermacher, J Boedo, R C Isler, A W Leonard,

More information

Perspective on Fusion Energy

Perspective 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 information

Design window analysis of LHD-type Heliotron DEMO reactors

Design window analysis of LHD-type Heliotron DEMO reactors Design window analysis of LHD-type Heliotron DEMO reactors Fusion System Research Division, Department of Helical Plasma Research, National Institute for Fusion Science Takuya GOTO, Junichi MIYAZAWA, Teruya

More information

US-Japan workshop on Fusion Power Reactor Design and Related Advanced Technologies, March at UCSD.

US-Japan workshop on Fusion Power Reactor Design and Related Advanced Technologies, March at UCSD. US-Japan workshop on Fusion Power Reactor Design and Related Advanced Technologies, March 5-7 28 at UCSD. Overview Overview of of Design Design Integration Integration toward toward Optimization -type

More information

Integrated Simulation of ELM Energy Loss and Cycle in Improved H-mode Plasmas

Integrated Simulation of ELM Energy Loss and Cycle in Improved H-mode Plasmas 1 Integrated Simulation of ELM Energy Loss and Cycle in Improved H-mode Plasmas N. Hayashi 1), T. Takizuka 1), N. Aiba 1), N. Oyama 1), T. Ozeki 1), S. Wiesen 2), V. Parail 3) 1) Japan Atomic Energy Agency,

More information

Nuclear Fusion and ITER

Nuclear Fusion and ITER Nuclear Fusion and ITER C. Alejaldre ITER Deputy Director-General Cursos de Verano UPM Julio 2, 2007 1 ITER the way to fusion power ITER ( the way in Latin) is the essential next step in the development

More information

A kinetic neutral atom model for tokamak scrape-off layer tubulence simulations. Christoph Wersal, Paolo Ricci, Federico Halpern, Fabio Riva

A kinetic neutral atom model for tokamak scrape-off layer tubulence simulations. Christoph Wersal, Paolo Ricci, Federico Halpern, Fabio Riva A kinetic neutral atom model for tokamak scrape-off layer tubulence simulations Christoph Wersal, Paolo Ricci, Federico Halpern, Fabio Riva CRPP - EPFL SPS Annual Meeting 2014 02.07.2014 CRPP The tokamak

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

EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE

EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE EFFECT OF EDGE NEUTRAL SOUCE PROFILE ON H-MODE PEDESTAL HEIGHT AND ELM SIZE T.H. Osborne 1, P.B. Snyder 1, R.J. Groebner 1, A.W. Leonard 1, M.E. Fenstermacher 2, and the DIII-D Group 47 th Annual Meeting

More information

The New Sorgentina Fusion Source Project

The New Sorgentina Fusion Source Project The New Sorgentina Fusion Source Project P. Agostini, P. Console Camprini, D. Bernardi, M. Pillon, M. Frisoni, M. Angelone, A. Pietropaolo, P. Batistoni, A. Pizzuto ENEA Agenzia Nazionale per le Nuove

More information

Impact of neutral atoms on plasma turbulence in the tokamak edge region

Impact of neutral atoms on plasma turbulence in the tokamak edge region Impact of neutral atoms on plasma turbulence in the tokamak edge region C. Wersal P. Ricci, F.D. Halpern, R. Jorge, J. Morales, P. Paruta, F. Riva Theory of Fusion Plasmas Joint Varenna-Lausanne International

More information

Plasma Spectroscopy Inferences from Line Emission

Plasma Spectroscopy Inferences from Line Emission Plasma Spectroscopy Inferences from Line Emission Ø From line λ, can determine element, ionization state, and energy levels involved Ø From line shape, can determine bulk and thermal velocity and often

More information

Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER

Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER M.L. Reinke 1, A. Loarte 2, M. Chilenski 3, N. Howard 3, F. Köchl 4, A. Polevoi 2, A. Hubbard 3, J.W. Hughes

More information

Plasma and Fusion Research: Regular Articles Volume 10, (2015)

Plasma and Fusion Research: Regular Articles Volume 10, (2015) Possibility of Quasi-Steady-State Operation of Low-Temperature LHD-Type Deuterium-Deuterium (DD) Reactor Using Impurity Hole Phenomena DD Reactor Controlled by Solid Boron Pellets ) Tsuguhiro WATANABE

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

Review of experimental observations of plasma detachment and of the effects of divertor geometry on divertor performance

Review of experimental observations of plasma detachment and of the effects of divertor geometry on divertor performance Review of experimental observations of plasma detachment and of the effects of divertor geometry on divertor performance Alberto Loarte European Fusion Development Agreement Close Support Unit - Garching

More information

ELM Suppression in DIII-D Hybrid Plasmas Using n=3 Resonant Magnetic Perturbations

ELM 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

Mission and Design of the Fusion Ignition Research Experiment (FIRE)

Mission and Design of the Fusion Ignition Research Experiment (FIRE) Mission and Design of the Fusion Ignition Research Experiment (FIRE) D. M. Meade 1), S. C. Jardin 1), J. A. Schmidt 1), R. J. Thome 2), N. R. Sauthoff 1), P. Heitzenroeder 1), B. E. Nelson 3), M. A. Ulrickson

More information

Nuclear Energy in the Future. The ITER Project. Brad Nelson. Chief Engineer, US ITER. Presentation for NE-50 Symposium on the Future of Nuclear Energy

Nuclear Energy in the Future. The ITER Project. Brad Nelson. Chief Engineer, US ITER. Presentation for NE-50 Symposium on the Future of Nuclear Energy Nuclear Energy in the Future The ITER Project Brad Nelson Chief Engineer, US ITER Presentation for NE-50 Symposium on the Future of Nuclear Energy November 1, 2012 Fusion research is ready for the next

More information

Introduction Introduction

Introduction Introduction 1 Introduction This book is an introduction to the theory of charged particle acceleration. It has two primary roles: 1.A unified, programmed summary of the principles underlying all charged particle accelerators.

More information

DIII D Research in Support of ITER

DIII D Research in Support of ITER Research in Support of ITER by E.J. Strait and the Team Presented at 22nd IAEA Fusion Energy Conference Geneva, Switzerland October 13-18, 28 DIII-D Research Has Made Significant Contributions in the Design

More information

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

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

More information

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

On Heat Loading, Novel Divertors, and Fusion Reactors. Abstract

On Heat Loading, Novel Divertors, and Fusion Reactors. Abstract On Heat Loading, Novel Divertors, and Fusion Reactors M. Kotschenreuther, P. M. Valanju, and S. M. Mahajan Institute for Fusion Studies, The University of Texas at Austin (Dated: March 22, 2006) Abstract

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

Aspects of Advanced Fuel FRC Fusion Reactors

Aspects of Advanced Fuel FRC Fusion Reactors Aspects of Advanced Fuel FRC Fusion Reactors John F Santarius and Gerald L Kulcinski Fusion Technology Institute Engineering Physics Department CT2016 Irvine, California August 22-24, 2016 santarius@engr.wisc.edu;

More information

Japan-US Workshop on Fusion Power Plants Related Advanced Technologies with participants from China and Korea (Kyoto University, Uji, Japan, 26-28

Japan-US Workshop on Fusion Power Plants Related Advanced Technologies with participants from China and Korea (Kyoto University, Uji, Japan, 26-28 Japan-US Workshop on Fusion Power Plants Related Advanced Technologies with participants from China and Korea (Kyoto University, Uji, Japan, 26-28 Feb. 2013) 2/22 FFHR-d1 R c = 15.6 m B c = 4.7 T P fusion

More information

Integration of Fokker Planck calculation in full wave FEM simulation of LH waves

Integration of Fokker Planck calculation in full wave FEM simulation of LH waves Integration of Fokker Planck calculation in full wave FEM simulation of LH waves O. Meneghini S. Shiraiwa R. Parker 51 st DPP APS, Atlanta November 4, 29 L H E A F * Work supported by USDOE awards DE-FC2-99ER54512

More information

Plasma impurity composition in Alcator C-Mod tokamak.

Plasma impurity composition in Alcator C-Mod tokamak. Plasma impurity composition in Alcator C-Mod tokamak. I. O. Bespamyatnov a, W. L. Rowan a, K. T. Liao a, M. Brookman a, M. L. Reinke b, E. S. Marmar b, M. J. Greenwald b a Institute for Fusion Studies,

More information

Temperature measurement and real-time validation

Temperature measurement and real-time validation Temperature measurement and real-time validation A. Herrmann, B. Sieglin, M. Faitsch, P. de Marné, ASDEX Upgrade team st IAEA Technical Meeting on Fusion Data Processing, Validation and Analysis ITER-

More information

Chapter 7 Plasma Basic

Chapter 7 Plasma Basic Chapter 7 Plasma Basic Hong Xiao, Ph. D. hxiao89@hotmail.com www2.austin.cc.tx.us/hongxiao/book.htm Hong Xiao, Ph. D. www2.austin.cc.tx.us/hongxiao/book.htm 1 Objectives List at least three IC processes

More information

DT Fusion Power Production in ELM-free H-modes in JET

DT Fusion Power Production in ELM-free H-modes in JET JET C(98)69 FG Rimini and e JET Team DT Fusion ower roduction in ELM-free H-modes in JET This document is intended for publication in e open literature. It is made available on e understanding at it may

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

Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER

Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER Tungsten impurity transport experiments in Alcator C-Mod to address high priority R&D for ITER A. Loarte ITER Organization, Route de Vinon-sur-Verdon, CS 90 046, 13067 St Paul Lez Durance Cedex, France

More information

The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions

The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions The EPED Pedestal Model: Extensions, Application to ELM-Suppressed Regimes, and ITER Predictions P.B. Snyder 1, T.H. Osborne 1, M.N.A. Beurskens 2, K.H. Burrell 1, R.J. Groebner 1, J.W. Hughes 3, R. Maingi

More information

The RFP: Plasma Confinement with a Reversed Twist

The RFP: Plasma Confinement with a Reversed Twist The RFP: Plasma Confinement with a Reversed Twist JOHN SARFF Department of Physics University of Wisconsin-Madison Invited Tutorial 1997 Meeting APS DPP Pittsburgh Nov. 19, 1997 A tutorial on the Reversed

More information

Which Superconducting Magnets for DEMO and Future Fusion Reactors?

Which Superconducting Magnets for DEMO and Future Fusion Reactors? Which Superconducting Magnets for DEMO and Future Fusion Reactors? Reinhard Heller Inspired by Jean Luc Duchateau (CEA) INSTITUTE FOR TECHNICAL PHYSICS, FUSION MAGNETS KIT University of the State of Baden-Wuerttemberg

More information

Evolution of the pedestal on MAST and the implications for ELM power loadings

Evolution of the pedestal on MAST and the implications for ELM power loadings Evolution of the pedestal on MAST and the implications for ELM power loadings Presented by Andrew Kirk EURATOM / UKAEA Fusion Association UKAEA authors were funded jointly by the United Kingdom Engineering

More information

NONLINEAR MHD SIMULATIONS OF ELMs IN JET

NONLINEAR MHD SIMULATIONS OF ELMs IN JET NONLINEAR MHD SIMULATIONS OF ELMs IN JET S.J.P. Pamela 1, G.T.A. Huysmans 1, M.N.A. Beurskens 2, S. Devaux 3, T. Eich 3, S. Benkadda 4 and JET EFDA contributors. 1 Association EURATOM-CEA, F-1318 Saint-Paul-lez-Durance,

More information

ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model

ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model 1 THC/3-3 ITER Predictions Using the GYRO Verified and Experimentally Validated TGLF Transport Model J.E. Kinsey, G.M. Staebler, J. Candy, and R.E. Waltz General Atomics, P.O. Box 8608, San Diego, California

More information

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

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

More information

PROGRESS IN STEADY-STATE SCENARIO DEVELOPMENT IN THE DIII-D TOKAMAK

PROGRESS IN STEADY-STATE SCENARIO DEVELOPMENT IN THE DIII-D TOKAMAK PROGRESS IN STEADY-STATE SCENARIO DEVELOPMENT IN THE DIII-D TOKAMAK by T.C. LUCE, J.R. FERRON, C.T. HOLCOMB, F. TURCO, P.A. POLITZER, and T.W. PETRIE GA A26981 JANUARY 2011 DISCLAIMER This report was prepared

More information

EFDA European Fusion Development Agreement - Close Support Unit - Garching

EFDA European Fusion Development Agreement - Close Support Unit - Garching Multi-machine Modelling of Divertor Geometry Effects Alberto Loarte EFDA CSU -Garching Acknowledgements: K. Borrass, D. Coster, J. Gafert, C. Maggi, R. Monk, L. Horton, R.Schneider (IPP), A.Kukushkin (ITER),

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

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

Influence of Impurity Seeding on ELM Behaviour and Edge Pedestal in ELMy H-Mode Discharges

Influence of Impurity Seeding on ELM Behaviour and Edge Pedestal in ELMy H-Mode Discharges EFDA JET CP()-5 S.Jachmich, G.Maddison, M.N.A.Beurskens, P.Dumortier, T.Eich, A.Messiaen, M.F.F.Nave, J.Ongena, J.Rapp, J.Strachan, M. Stamp, W.Suttrop, G.Telesca, B.Unterberg and JET EFDA Contributors

More information

Influence of gas impuritites on plasma performance on JET tokamak

Influence of gas impuritites on plasma performance on JET tokamak 19 Influence of gas impuritites on plasma performance on JET tokamak Martin Kubič České vysoké učení technické v Praze Fakulta jaderná a fyzikálně inženýrská Katedra fyziky THERMONUCLEAR FUSION 1.1 Introduction

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

Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET

Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET Journal of Nuclear Materials 363 365 (2007) 989 993 www.elsevier.com/locate/jnucmat Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET T. Eich a, *, A.

More information

Tritium Transport Modelling: first achievements on ITER Test Blanket Systems simulation and perspectives for DEMO Breeding Blanket

Tritium Transport Modelling: first achievements on ITER Test Blanket Systems simulation and perspectives for DEMO Breeding Blanket Tritium Transport Modelling: first achievements on ITER Test Blanket Systems simulation and perspectives for DEMO Breeding Blanket I. Ricapito 1), P. Calderoni 1), A. Ibarra 2), C. Moreno 2), Y. Poitevin

More information

Multiple hydrogen trapping by vacancies: Its impact on defect dynamics and hydrogen retention in tungsten

Multiple hydrogen trapping by vacancies: Its impact on defect dynamics and hydrogen retention in tungsten 2014 Joint ICTP-IAEA Conference on Models and Data for Plasma-Material Interaction in Fusion Devices, 3 7 November 2014, International Centre for Theoretical Physics (ICTP), Trieste, Italy. Multiple hydrogen

More information

Fusion Research at the ASDEX Upgrade Tokamak Experiences with Tungsten Plasma Facing Components

Fusion Research at the ASDEX Upgrade Tokamak Experiences with Tungsten Plasma Facing Components Fusion Research at the ASDEX Upgrade Tokamak Experiences with Tungsten Plasma Facing Components Magnetically Confined Fusion Towards ITER Results with Tungsten PFCs in ASDEX Upgrade R. Neu and ASDEX Upgrade

More information

Design Windows and Economic Aspect of Helical Reactor

Design Windows and Economic Aspect of Helical Reactor Design Windows and Economic Aspect of Helical Reactor Y. Kozaki, S. Imagawa, A. Sagara National Institute for Fusion Science, Toki, Japan Japan-US Workshop, Kashiwa, March 16-18,2009 - Background and Objectives

More information

Chapter 7. Plasma Basics

Chapter 7. Plasma Basics Chapter 7 Plasma Basics 2006/4/12 1 Objectives List at least three IC processes using plasma Name three important collisions in plasma Describe mean free path Explain how plasma enhance etch and CVD processes

More information

Production of Over-dense Plasmas by Launching. 2.45GHz Electron Cyclotron Waves in a Helical Device

Production of Over-dense Plasmas by Launching. 2.45GHz Electron Cyclotron Waves in a Helical Device Production of Over-dense Plasmas by Launching 2.45GHz Electron Cyclotron Waves in a Helical Device R. Ikeda a, M. Takeuchi a, T. Ito a, K. Toi b, C. Suzuki b, G. Matsunaga c, S. Okamura b, and CHS Group

More information

Massachusetts Institute of Technology 22.68J/2.64J Superconducting Magnets. February 27, Lecture #4 Magnetic Forces and Stresses

Massachusetts 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 information

Evaluation of CT injection to RFP for performance improvement and reconnection studies

Evaluation of CT injection to RFP for performance improvement and reconnection studies Evaluation of CT injection to RFP for performance improvement and reconnection studies S. Masamune A. Sanpei, T. Nagano, S. Nakanobo, R. Tsuboi, S. Kunita, M. Emori, H. Makizawa, H. Himura, N. Mizuguchi

More information

Chamber Development Plan and Chamber Simulation Experiments

Chamber Development Plan and Chamber Simulation Experiments Chamber Development Plan and Chamber Simulation Experiments Farrokh Najmabadi HAPL Meeting November 12-13, 2001 Livermore, CA Electronic copy: http://aries.ucsd.edu/najmabadi/talks UCSD IFE Web Site: http://aries.ucsd.edu/ife

More information

Dynamic measurement of the helium concentration of evolving tungsten nanostructures using Elastic Recoil Detection during plasma exposure

Dynamic measurement of the helium concentration of evolving tungsten nanostructures using Elastic Recoil Detection during plasma exposure PSFC/JA-14-38 Dynamic measurement of the helium concentration of evolving tungsten nanostructures using Elastic Recoil Detection during plasma exposure Woller, K.B., Whyte, D.G., Wright, G.M. January,

More information

Conceptual Design of CFETR Tokamak Machine

Conceptual Design of CFETR Tokamak Machine Japan-US Workshop on Fusion Power Plants and Related Advanced Technologies February 26-28, 2013 at Kyoto University in Uji, JAPAN Conceptual Design of CFETR Tokamak Machine Yuntao Song for CFETR Design

More information

Plans for a laboratory electron-positron plasma experiment

Plans for a laboratory electron-positron plasma experiment Plans for a laboratory electron-positron plasma experiment Thomas Sunn Pedersen, Xabier Sarasola Max-Planck Institute for Plasma Physics, Germany Lutz Schweikhard, Gerrit Marx Ernst-Moritz Arndt Universität

More information

A novel tracer-gas injection system for scrape-off layer impurity transport and screening experiments

A novel tracer-gas injection system for scrape-off layer impurity transport and screening experiments A novel tracer-gas injection system for scrape-off layer impurity transport and screening experiments B. LaBombard, S. Gangadhara, B. Lipschultz, S. Lisgo a, D.A. Pappas, C.S. Pitcher, P. Stangeby a, J.

More information

GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME

GA 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 information

Reinstallation of the COMPASS D Tokamak in IPP ASCR

Reinstallation of the COMPASS D Tokamak in IPP ASCR R. Pánek, O. Bilyková, V. Fuchs, M. Hron, P. Chráska, P. Pavlo, J. Stöckel, J. Urban, V. Weinzettl, J. Zajac and F. Žáček Institute of Plasma Physics, Academy of Sciences of the Czech Republic, Za Slovankou

More information

Analytical Study of RWM Feedback Stabilisation with Application to ITER

Analytical 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 information

The Physics Basis of ITER Confinement

The Physics Basis of ITER Confinement The Physics Basis of ITER Confinement F. Wagner Max-Planck-Institut für Plasmaphysik EURATOM Association Wendelsteinstr. 1, 17491 Greifswald, Germany Abstract. ITER will be the first fusion reactor and

More information

Seminar Chengdu, China Southwestern Institute of Physics (SWIP)

Seminar Chengdu, China Southwestern Institute of Physics (SWIP) Blanket/First Wall Challenges and Required R&D on the pathway to DEMO for the near term in laboratory experiments and medium term in FNSF/CFETR Mohamed Abdou Distinguished Professor of Engineering and

More information

Estimating the plasma flow in a recombining plasma from

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

More information

Heat Transport in a Stochastic Magnetic Field. John Sarff Physics Dept, UW-Madison

Heat Transport in a Stochastic Magnetic Field. John Sarff Physics Dept, UW-Madison Heat Transport in a Stochastic Magnetic Field John Sarff Physics Dept, UW-Madison CMPD & CMSO Winter School UCLA Jan 5-10, 2009 Magnetic perturbations can destroy the nested-surface topology desired for

More information

Superconducting Magnet Design and R&D with HTS Option for the Helical DEMO Reactor

Superconducting Magnet Design and R&D with HTS Option for the Helical DEMO Reactor Superconducting Magnet Design and R&D with HTS Option for the Helical DEMO Reactor N. Yanagi, A. Sagara and FFHR-Team S. Ito 1, H. Hashizume 1 National Institute for Fusion Science 1 Tohoku University

More information

S1/2 EX/S, EX/D, EX/W

S1/2 EX/S, EX/D, EX/W S1/2 EX/S, EX/D, EX/W S1/2 EX/S - Magnetic Confinement Experiments: Stability 47 papers EX/W - Magnetic Confinement Experiments: Wave plasma interactions, current drive & heating, energetic particles 58

More information

TH/P6-14 Integrated particle simulation of neoclassical and turbulence physics in the tokamak pedestal/edge region using XGC a)

TH/P6-14 Integrated particle simulation of neoclassical and turbulence physics in the tokamak pedestal/edge region using XGC a) 1 TH/P6-14 Integrated particle simulation of neoclassical and turbulence physics in the tokamak pedestal/edge region using XGC a) 1 Chang, C.S., 1 Ku, S., 2 Adams M., 3 D Azevedo, G., 4 Chen, Y., 5 Cummings,

More information

Rotation and Neoclassical Ripple Transport in ITER

Rotation 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 information

Divertor Detachment on TCV

Divertor Detachment on TCV Divertor Detachment on TCV R. A. Pitts, Association EURATOM-Confédération Suisse,, CH- LAUSANNE, Switzerland thanks to A. Loarte a, B. P. Duval, J.-M. Moret, J. A. Boedo b, L. Chousal b, D. Coster c, G.

More information

Non-linear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations.

Non-linear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations. Non-linear MHD Modelling of Rotating Plasma Response to Resonant Magnetic Perturbations. M. Becoulet 1, F. Orain 1, G.T.A. Huijsmans 2, G. Dif- Pradalier 1, G. Latu 1, C. Passeron 1, E. Nardon 1, V. Grandgirard

More information

The Advanced Tokamak: Goals, prospects and research opportunities

The Advanced Tokamak: Goals, prospects and research opportunities The Advanced Tokamak: Goals, prospects and research opportunities Amanda Hubbard MIT Plasma Science and Fusion Center with thanks to many contributors, including A. Garafolo, C. Greenfield, C. Kessel,

More information

Hard Xray Diagnostic for Lower Hybrid Current Drive on Alcator C- Mod

Hard Xray Diagnostic for Lower Hybrid Current Drive on Alcator C- Mod Hard Xray Diagnostic for Lower Hybrid Current Drive on Alcator C- Mod J. Liptac, J. Decker, R. Parker, V. Tang, P. Bonoli MIT PSFC Y. Peysson CEA Cadarache APS 3 Albuquerque, NM Abstract A Lower Hybrid

More information