A Joint Australian Fusion Energy Initiative Strategic plan for Fusion Science – ITER forum – Capability, infrastructure, Flagship Diagnostic? Initial ISL.

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Presentation transcript:

A Joint Australian Fusion Energy Initiative Strategic plan for Fusion Science – ITER forum – Capability, infrastructure, Flagship Diagnostic? Initial ISL projects – Howard $0.5M, Hole et al $0.4M Next Step ? Clean Energy Fund? $3M Govt, $3M others Expertise: – plasma diagnostics: typically spectroscopy and laser (ANU, Syd, Macq) – Exotic and high temperature materials (ANSTO, Unew,Syd, ANU….) – peculiar plasma shapes (heliac) – Theory  Divertors and plasma walls! couple with “unclaimed” ITER diagnostic subsystems

Tile 4 Pumping slots Flaked-off deposited films and dust: JET Divertor J.P. Coad, 1998

1) Erosion Measurement system –There are 2 LASER based depth probing techniques (LASER radar 1 & Speckle interferometry 2 ) which meet ITER requirements if a 2-wavelength system is used. –Measure net effect of erosion and deposition –No Tokamak tested prototype, however, LASER radar used off-line on TFTR –need reference point to distinguish erosion from vessel/divertor displacement –from dome, target strike zones are visible (change in divertor profile) [1] K Itami et al [2] P. Dore et al Dore P and Gauthier E 2006 Speckle interferometry: a diagnostic for erosion-redeposition measurements in fusion devices 17th Int. Conf. on Plasma Surface Interaction in Controlled Fusion Devices (Hefei, China, 22–6 May 2006)

The University of Sydney AUSTRALIA Australian Nuclear Science &Tec. Org. Atomic and molecular physics modeling Quasi-toroidal pulsed cathodic arc Plasma theory/ diagnostics Dusty Plasmas joining and material properties under high heat flux Plasma spectroscopy MHD and kinetic theory Materials science analysis High heat flux alloys MAX alloys synthesis Materials characterisation High temperature materials Manages OPAL research reactor Wider Australian fusion-relevant capabilities Faculty of Engineering

Good thermal, electrical conductor high melting point ideally composed of low Z specie not retain too much hydrogen high resistance to thermal shocks heat load of MW m MeV neutron irradiation 10 keV D, T, He bombardment MAX alloys are one promising route : M = transition metal (Sc, Ti, V, Cr, Zr, Nb, Mo, Hf, Ta) A = Al, Si, P, S, Ga, Ge, As, Cd, In, Sn, Tl, Pb X = either C or N Different Stochiometries  over 600 potential alloys. Spectroscopy lab The first wall of a fusion reactor has to cope with the ‘environment from hell’ so it needs a ‘heaven sent surface’. A sample of Material Science research in Australian Universities – Newcastle Univ. also University of Sydney, Melbourne

Finite-  equilibria in H-1NF Vacuum  = 1%  = 2% Island phase reversal: self-healing occurs between 1 and 2%  Enhanced HINT code of late T. Hayashi, NIFS S. Lloyd (ANU PhD), H. Gardner

MRXMHD: Multiple relaxation region model for 3D plasma equilibrium Motivation: In 3D, ideal MHD (A) magnetic islands form on rational flux surfaces, destroying flux surface (B) equilibria have current singularities if  p  0 Present Approach: ignore islands (eg. VMEC ), or adapt magnetic grid to try to compensate (PIES). Latter cannot rigorously solve ideal MHD – error usually manifest as a lack of convergence. Different  in each region ANU/Princeton project: To ensure a mathematically well- defined J , we set  p = 0 over finite regions   B =  B,  = const (Beltrami field) separated by assumed invariant tori.

Prof. I. Bray: Curtin University Presentation to IAEA 2009

Atomic Cross-Sections for ITER World-leading calculation of atomic cross-sections relevant to fusion using their “Convergent Close Coupling” (CCC) Method Recent study of U 91+, Li, B3+ and Tungsten (W 73+ ) for ITER

12 IEC: Doppler spectroscopy in H 2 : Predicting experimental fusion rates IEC: Doppler spectroscopy in H 2 : Predicting experimental fusion rates J. Kipritidis & J. Khachan

13 Results: sample H α spectrum at the anode wall (Summed H 2 +, H 3 + ) This peak used for prediction

14 Results: neutron counts! (constant voltage) PhysRevE 2009 Densities of fast H at the cathode aperture are ~ 1-10 x m -3 Dissociation fractions f fast at apertures are ~ (increases with current!) Slope=1 line (Summed H 2 +, H 3 + ) Supports neutral on neutral theory: Shrier, Khachan, PoP 2006

Levitation of Different Sizes Particles - Samarian Probing of sheath electric field on different heights RF Sheath Diagnostic Levitation Height Powered Electrode 2.00 micrometer dust 3.04 micrometer dust 3.87 micrometer dust 4.89 micrometer dust 6.76 micrometer dust Sheath Edge Bulk Plasma Sub-micron dust cloud Sub-micron particles

Dust Deflection in IEC Fusion Device – Samarian/Khachan IEC Diagnostic Dust particle being deflected towards the rings are visible on the left hand side IEC ring electrodes (cathode) Phys Letts A 2007

ANU - University of Sydney collaboration Development of a He pulsed diagnostics beam Te profiles measured in H-1NF, from He line intensity ratios, with aid of collisional radiative model John Howard Scott Collis Robert Dall Brian James Daniel Andruczyk

Experimental set-up

SkimmerPulsed Valve Pulsed He source Collection optics

Spectral line emissivity vs radius beam emissivity falls as beam moves into the plasma due to progressive ionization T e vs radius

ResearchExamples from H-1 Effect of Magnetic Islands on Plasma Alfven Eigenmodes in H-1

ResearchExamples from H-1 Effect of Magnetic Islands on Plasma Alfven Eigenmodes in H-1

H-1 Heliac: parameters Machine class3-period heliac Major radius, R1m Minor radius, a m Vacuum volume, V33 m 2 (excellent access) Toroidal field, B   1 Tesla (0.2 DC) Aspect Ratio (R/ ) 5 + (Toroidal > Helical) Heating Power, P 0.2MW (28 GHz ECH) 0.3MW (6-25MHz ICH) Plasma parameters AchievedDesign electron density 3  m m -3 electron temp., T150eV500eV Plasma beta,  0.2 %0.5%

H-1 configuration (shape) is very flexible “flexible heliac” : helical winding, with helicity matching the plasma,  2:1 range of twist/turn H-1NF can control 2 out of 3 of transform (  ) magnetic well and shear  ( spatial rate of change) Reversed Shear  Advanced Tokamak mode of operation Edge Centre low shear medium shear  = 4/3  = 5/4 24 Blackwell, International Meeting on the Frontiers of Physics, Malaysia 2009

Blackwell, ISHW/Toki Conference 10/2007 Experimental confirmation of configurations Rotating wire array 64 Mo wires (200um) angles High accuracy (0.5mm) Moderate image quality Always available Excellent agreement with computation Santhosh Kumar

Mapping Magnetic Surfaces by E-Beam Tomography: Raw Data Blackwell, Kyoto JOB 16 th March 2009 M=2 island pair Sinogram of full surface For a toroidal helix, the sinogram looks very much like part of a vertical projection (top view)

Good match confirms island size, location Good match between computed and measured surfaces Accurate model developed to account for all iota (NF 2008) Minimal plasma current in H-1 ensures islands are near vacuum position Sensitive to shear identify sequence number  high shear surfaces “smear” Blackwell, Kyoto JOB 16 th March 2009 Iota ~ 3/2 Iota ~ 1.4 (7/5) computed + e-beam mapping (blue/white )

Effect of Magnetic Islands Giant island  “flattish” density profile Central island – tends to peakPossibly connected to core electron root enhanced confinement 28Blackwell, International Meeting on the Frontiers of Physics, Malaysia 2009

Spontaneous Appearance of Islands Iota just below 3/2 – sudden transition to bifurcated state Plasma is more symmetric than in quiescent case. Uncertainty as to current distribution (and therefore iota), but plausible that islands are generated at the axis. If we assume nested magnetic surfaces,  then we have a clear positive Er at the core – similar to core electron root configuration? Many unanswered questions…… Symmetry? How to define Er with two axes? Blackwell, Kyoto JOB 16 th March 2009

Identification with Alfvén Eigenmodes: n e Coherent mode near iota = 1.4, 26-60kHz, Alfvénic scaling with n e Poloidal mode number (m) resolved by “bean” array of Mirnov coils to be 2 or 3. V Alfvén = B /  (  o  )  B /  n e Scaling in  n e in time (right) and over various discharges (below) phase 1/ne1/ne nene f  1 /  n e Critical issue in fusion reactors: V Alfvén ~ fusion alpha velocity  fusion driven instability! 30Blackwell, International Meeting on the Frontiers of Physics, Malaysia 2009

Fluctuation Spectra Data from Interferometer upgrade: (Rapid electronic wavelength sweep) Fluctuation spectra Profiles Turn-key Fast sweep <1ms D Oliver

Alfven Mode Decomposition by SVD and Clustering Initial decomposition by SVD  ~ eigenvalues Remove low coherence and low amplitude Then group eigenvalues by spectral similarity into fluctuation structures Reconstruct structures to obtain phase difference at spectral maximum Cluster structures according to phase differences (m numbers)  reduces to 7-9 clusters for an iota scan Grouping by SVD+clustering potentially more powerful than by mode number – Recognises mixtures of mode numbers caused by toroidal effects etc – Does not depend critically on knowledge of the correct magnetic theta coordinate 4 Gigasamples of data –128 times –128 frequencies – 2 C 20 coil combinations –100 shots increasing twist 