Research on controlled fusion at the Institute of Plasma Physics in Kharkiv Presented by V.E. Moiseenko on behalf of IPP-Kharkiv research team NATIONAL SCIENCE CENTER "KHARKOV INSTITUTE OF PHYSICS AND TECHNOLOGY" INSTITUTE OF PLASMA PHYSICS The Main Directions of Plasma research at IPP NSC KIPT 1. Fusion Investigations (theory and experiment) 1.1. Magnetic confinement of plasma in stellarators and electro- magnetic traps. 1.2. High frequency methods of plasma heating. 1.3. Diagnostic methods of high temperature plasma. 2. Powerful pulsed and quasi-steady-state plasma accelerators and their applications. 3. Problems of fusion reactor ITER 3.1. Problems of divertor and its materials. 3.2. First mirrors of diagnostic systems. 4. Plasma technologies. 5. Fundamental problems of plasma physics. All experimental devices related to fusion at Ukraine are located in IPP NSC KIPT. Significant part of fusion theoretical research ia also carried on here. 2 Infrastructure
• 3 buildings: 2 with office area (19,000 m2) and 3 experimental halls (2x1,200 m2 and 1,500 m2 ) and one for power supply; • 2 workshops;
• Water supply and electricity (1 MWe); • Two experimental installations of stellarator type; • Two quasi-stationary plasma accelerators (QSPA); • Tens small plasma devices.
Stellarator
• Stellarator is a toroidal device for plasma confinement with magnetic field; • Stellarator has magnetic surfaces in vacuum that exist without plasma currents; • Cons: stellarator has worse plasma confinement and lower beta than tokamak; • Pros: stellarator can provide stationary operation and less subjected to uncontrolled MHD phenomena; • Stellarator remains a candidate as a fusion reactor machine. • Stellarators in EU: W-7X, TJ-II, Vega
Uragan-3M
Uragan-3M is a small size torsatron with l=3, m=9, R0=1 m major radius, a 0.12 m average plasma radius and toroidal magnetic field B0 1 T. The whole magnetic system is enclosed into a large 5 m diameter vacuum chamber.
In experiments B0~0.7 T Uragan-2M device It has both helical and toroidal field coils Major radius R=1.7 m Minor plasma radius – a 0.24m
Toroidal magnetic field - B0 2.4 Т For K =0.31 (0)=0.34, (a)=0.47 Pumping rate 2x400 dm3/s Plasma production and heating in K is a ratio of the toroidal magnetic U-2M is performed by the RF field induced by the helical winding to power. the total toroidal field Initial goal of the device is studying of the magnetic confinement. After accidentalInitial aim ofinjection the device of is studyingthe vacuum oil from the pumping system to the vacuum chamber the studies become restricted to RF wall conditioning and support of the fusion-fission hybrid development. Studies on divertor flows in Uragan-3M CHARACTERISTICS OF THE HELICAL DIVERTOR OF THE URAGAN-3M TORSATRON A strong up-down asymmetry of plasma flows has been observed for the first time in the helical divertor of the Heliotron E heliotron/torsatron under ECRH and NBI conditions. А similar effect has been also revealed and studied in the U- 3M torsatron with an open natural helical divertor and a plasma RF-produced and -heated in the ω≲ωci range of frequencies. To detect divertor plasma flows (DPF) arrays of plane electric probes are used. Main characteristics of the asymmetry: - the larger ambipolar DPF on the ion ∇B drift side (“ion side”);
- floating potential Vf and plasma current (current to the earthed probe) in DPF are positive on the ion side and negative on the electron side. Conclusion: the asymmetry is caused by the direct (non-diffusional) particle loss. Confirmed by: (1) measurements of ion energy in the DPF on the ion and electron sides, (2) a rising dependence of asymmetry degree on the fast ion content, and (3) numerical modeling of direct losses.
V.V. Chechkin et al 2002 Nucl. Fusion 42 192 Runaway electrons at Uragan-3M
Magnetic field evolution and signals of ECE, Rogovski coil, and x-ray detector for antenna voltages: +100V (left) , +20V (center) and -100V (right).
Introduction of small negative electrostatic field to the confinement volume stops runaway electron avalanche
V.E. Moiseenko et al Technical Physics Letters, 40 (2014) pp.669-672 Alfven resonance heating
• We suggest to use compact antennas for AR heating that makes is competitive to ICRH; • The advantage of AR heating is that it is applicable both for small and big devices; • At big scale, the heating frequency is low and highly efficient RF generators could be used; • AR heating delivers energy to bulk plasma electrons and does not cause the instabilities of TAE and other modes. This is very advantageous for alpha-particles confinement. Alfvén resonance heating scheme KAW
SQEW
v Te v A v Te v A
Plasma density Plasma Fast wave field
antenna FAW
, v A / k ||
Radius 2 2 Alfvén resonance condition , where k = щ/ c k|| = k0 е 0 2 2 2 2 2 1pB /( ) FAW cut-off condition k|| = k0 (е + g)
k|| =(n+m/ q)/ R V.E. MOISEENKO et al, Plasma Physics Reports 35 (2009) 828. Alfvén heating strategies
Alfvén heating: no propagating wave excitation => small antenna loading, big antenna Q
Position of Alfvén resonance depends on k|| value => periphery heating possible
• Two strategies for Alfvén heating: No periphery heating • Strict: remove all Periodic antenna occupies large small k|| from the space antenna spectrum Sensitivity to plasma density • Loose: concentrate antenna spectrum around selected k|| Periphery heating Relatively compact antenna No sensitive dependences on plasma parameters Compact antennas for Alfven resonance heating
Uragan-3M antennas inside the vacuum vessel: THT antenna (left) and frame antenna (right). THT antenna is fed by K2 generator with frequency 8.8 MHz. Frame antenna is connected to K1 generator with frequency 8.6 MHz. The discharge is initiated by the frame antenna. Evolution of plasma parameters PROS: •Plasma with density 2x1012- 13 -3 280 2x10 cm is created and 7 P , kW 260 U heated by the THT antenna; 2 240 P , kW 6 U •Plasma is fully ionized and
220 1 , kW 2 12 -3 have a temperature ~50 eV. U 200 n , 10 cm e
P 5
180 T , a.u. (soft X-ray) n e e , 10 , CONS:
160 4 , kW 1 140
12 •The energy confinement time U
cm P 120 3 given by ratio of the plasma 100 -3 energy content to the heating
, a.u. 80 2 e
T 60 power gives low values (0.1-0.2 40 1 ms) 20 •The estimate for particle 0 0 0 10 20 30 40 50 60 70 80 90 100 confinement time as ratio of t, ms particle content to the influx of neutral gas is also low (0.5-1.5 ms) Time evolutions of average plasma density, average •There is a discrepancy in the electron temperature and RF power launched to plasma. electron temperature values Neutral gas pressure is 8x10-6 Torr. given by SXR and ECE diagnostics Spectral lines: H
The central region
H-gamma radial Low threshold line emissions: CIII and OV
High level emission of such impurities is normally observed in CIII radial Frame THT low temperature plasma (Te<100 eV), and this takes place at outer part of the plasma column
OV radial CV line emission and radiation temperature by ECE
CV line emission is located at the central region of the plasma column. The temperature localization is even stronger. After power Frame THT CV radial switch-off, the longest decay time is at the 500 eV magnetic axis
0
Radiation temperature Uragan-3M magnetic configurations
z, cm z, cm
R, cm R, cm
The regular magnetic configuration of Uragan-3M (left figure) has
• Spectroscopy and ECE data indicate that there are two regions in Uragan- 3M with different plasma energy confinement: the central region
Frame antenna 4-strap antenna Small frame antenna
New central strap of crankshaft antenna
Crankshaft antenna U-2M RF discharge
The discharge parameters are B0=0.37 T, -3 pH2=10 Pa. A small-power frame antenna pulse (f=3.9 MHz) goes first (t=10-16 ms) and makes the target plasma. The crankshaft antenna pulse (f=4.2 MHz)
goes second (t=16-24 ms). PRF 150 kW. The light impurity radiation barrier is Time dependence of electron passed at the beginning of the discharge. temperature evaluated from SXR After few ms the discharge fades owing to measurements and optical emission contamination by impurities. (a.u.). Vertical magenta dotted lines indicate start and stop of the crankshaft antenna RF pulse U-2M short RF discharge
This discharge is as previous, but the crankshaft antenna pulse terminates earlier (t=19 ms). The light impurity radiation barrier is passed at the beginning of the discharge. No contamination by impurities is observed.
Time dependence of optical emissions (a.u.) Chord measurements of optical emissions
The chord measurements of CV and OV line intensities are made shot by shot. The coverage area is central. The chord parameter is z coordinate of the chord footprint at the opposite wall of the vacuum chamber CV and OV emissions
k =0,34 FULL CONFIGURATION k =0,34 FULL CONFIGURATION t,ms 23.03.2015 t,ms 6000 17,5 17 8000 25.03.2015 17,5 I =100A 18 cor 18 18,5 I =100A 4000 19 6000 cor 18,5 19,5 19
, a.u. 20 4000 19,5
, a.u. CV
I 2000 20
20,5 OV I 20,5 21 2000 21
-6 -4 -2 0 2 4 6 8 10 6000 -6 -4 -2 0 2 4 6 8 10 p, cm 8000 p, cm I =250A I =250A cor cor 4000 6000
4000
, a.u.
, a.u. OV
CV 2000 I I 2000
-6 -4 -2 0 2 4 6 8 10 -6 -4 -2 0 2 4 6 8 10 p, cm p,cm The chord distribution of CV is flattened, especially for the maximum intensities (at t=19.5 ms). OV distribution is hollow. This indicates existence of hollow profiles and presence of C5+ and O5+ ions in the discharge. Independent operation of crankshaft antenna
With a new, more wiggled central strap, the crankshaft antenna is able to create plasma independently
Time dependence of optical emissions (a.u.) RF wall conditioning
Purpose: •Removing impurities accumulated at the vacuum chamber Cleaning by hydrogen atoms: •Chemical mechanism •Continuous or pulse regime •Uniform cleaning along the surface •Low plasma density and temperature (every electron produces many dissociations during lifetime) Wall conditioning in Uragan-3M by pulsed discharge Wall conditioning is performed at low magnetic field B=0.01-0.03 T. Hydrogen pressure is 10-2 Pa. The frequencies of both generators are in the range 8-9 MHz. The electron temperature is kept low, about 10 eV, to provide efficient Time evolution of plasma density. generation of hydrogen atoms.
A. V. Lozin, et al, Plasma Physics Reports, 2013, Vol. 39,p. 624
Residual gas partial pressures at the beginning and at the end Time evolution of RF powers delivered to of wall conditioning. frame (black curve) and THT (grey curve) - CnHm(CH2+CH4+C2H4); - Ar; - CO+N2; - H2O. antennas. VHF wall conditioning continuous discharge in Uragan-2M
Dependence of hydrogen Small frame antenna atoms density on neutral gas pressure (optical Wall conditioning is measurements). performed at low magnetic field B=0.01-0.03 T. Hydrogen pressure is 10-2 Pa. The frequency is 140 MHz. Plasma density and electron temperature radial profiles during VHF discharge at magnetic field 0.03 T. V.E. Moiseenko, et al, Nucl. Fusion 54 (2014) 033009. Need for transmutation of spent nuclear fuel • Currently almost all the amount of spent nuclear fuel is stored in the geological repositories; • Storage time is approximately 300,000 years while the separated fission products should be stored 300 years; • The storing and maintenance is costly (in aggregate), the storage may be destroyed by earthquakes and may be subjected by robbery by terrorists for making ‘dirty’ bomb; • The spent nuclear fuel contains mainly fissile material part of which could burned in fast reactors with energy extraction. The main obstacle for this is that the plutonium that is the majority of the burnable components provides little delayed neutrons which are important for reactor control. Subcritical system
•Does not require delayed neutrons •Can burn minor actinides •Has improved controllability and safety
f ,i i Ni i keff
( f ,i c,i )Ni loss i
For a fusion driver: Fusion minimum Q~0.1 Usage of sloshing ions Straight Field line Mirror (SFLM): particles move without drift In vacuum:
Two extra constants of motion at SFLM:
AGREN O. et al Phys. Rev. E. 72 (2005) 26408-1-5. In general quadrupolar mirror particle has a banana trajectory. The banana slowly rotates around the magnetic axis. The radial invariant exists in quadrupolar mirror. O. Ågren and V. E. Moiseenko Plasma Phys. Control. Fusion 56 (2014) 095026 Stellarator-mirror hybrid MOISEENKO V.E., et al J Fusion Energy 29 (2010) 65.
NBI •To drive a sub-critical system, the neutrons are Fission reacto generated in deuterium-tritium plasma confined r Neutron magnetically in a stellarator-type system. Plasma capturer Fusion contains warm electron component. The majority of neutron flux ions (deuterium) are in thermal equilibrium with the electrons.
•Stellarator provides steady-state operation of the Background plasma device and offers relatively good confinement for such warm Maxwellian plasma. The hot minority tritium ions Stellarator are sustained in plasma by radio-frequency (RF) par t heating or NBI. Since high energy ions are poorly confined in stellarator, it is proposed to embed into Mirror part those in a mirror trap with lower magnetic field.
Magnetic coils •The hot ions have velocities predominantly perpendicular to the confining magnetic field. Because of mirror trapping effect, their motion is restricted to the Transmutation scenario: mirror part of the device. The localization of the hot Uranium and fission products to be separated from the spent sloshing ions and the neutron generating zone to the nuclear fuel; mirror part is beneficial. Metallic or MOX fuel is prepared from the residue; The energy of the fuel is aps. 1/3 of the initial U235 energy; •It allows to surround the neutron generating zone by a local fission mantle and place all the plasma The fuel is burned in a sub-critical fast reactor and the diagnostics and plasma control aside the fission reactor electricity is generated. where the neutron flux is low.
V. E. Moiseenko, et al, Plasma Phys. Control. Fusion 56 (2014) 094008. Sub-Critical fission mantle
• Total power generated by neutrons in the first wall amount to ≈ 3.7 MW/m3;
• The fusion neutrons deliver to the first wall 0.54 MW, fission neutrons 0.5 MW, the surface heat load from the plasma heating is 3.4 MW and from the alpha particles is 1.25 MW. The total power delivered to the first wall is 5.7 MW. This is equivalent to 0.45 MW/m2 of average surface heat load with maximum value of 0.5 MW/m2. This is below representative values for fusion reactors which are expected to be greater than 1 MW/m2;
• The first wall accumulates 30 DPA during a 365 effective full power days;
• Tritium breeding ratio (TBR) is equal 1.75. CALCULATION RESULTS (MCNPX):
• Effective multiplication factor is keff = 0.95087 0.00017; Chernitskiy S.V. et al., Annals of Nuclear Energy.
2014, V.72, pp. 413-420. • The fission power Pfis≈1100 MW for a neutron source with intensity 6 1018 neutrons per second; Chernitskiy S.V. et al., Fusion Science and Tech., V. 63, Number 1T, May 2013, pp. 322-324. • Total power delivered into the magnetic coils which surround the reactor mantle will not exceed the value of 5.7 kW;
• The spectrum of the neutron flux; SM hybrid features • The device is capable to provide steady-state operation (for a year or more) .
• It is expected that the full control on plasma could be achieved: there would be no any disruption or spontaneous instabilities which seriously influences on neutron generation.
• The neutron outflow is tuneable and the response time is short enough to provide full control on power generation.
• The design and operation of all plasma device systems is facilitated with a localization of the neutron emission.
• In a wide range of the machine parameters, a high electric Q is calculated.
• In a power plant scale the plasma part of the considered FDS machine is compact enough with a size comparable to existing fusion devices.
• An experimental device could be built in small scale for a proof-of-principle purpose, and even under these conditions it may have a positive power output.
• Reproduction of tritium can be provided. Kinetic calculations Sloshing tritium ions NBI generates ions with perpendicular energy at R=1.3. 8 3.4 3.2 Small mirror ratio as R=1.7 is sufficient to confine the
7 y
t 3.0 i
c sloshing ions. A change of the mirror ratio from R=1.7 to R=2
2.8
o l
e 6 2.6 v
increases the hot ion content only by 1%, and the mean ion
r 2.4
a l
u 5 2.2
c energy also remains almost unchanged. i
d 2.0 n
e 4 1.8
p r
e 1.6 p 1.4 The electron drag takes 62% of the injected power, the ion-
d 3 e
z 1.2
i l
a 2 1.0 ion collisions 19%. The remainder goes to the loss cone m r 0.8 o and is lost due to finite confinement time at the mirror part N 1 0.6 0.4 of the device. 0.2 1 2 3 4 5 6 Normalized parallel velocity Contours of distribution function. Dashed line shows boundary Neutron emission intensity for between trapped and passing Einj=300keV and two different particles. T=3 keV background plasma temperatures. T=0,8 keV Netronflux density,line a.u. -1,5 -1 -0,5 0 0,5 1 1,5 Normalized length V. E. Moiseenko, O. Ågren Fusion Sc. and Tech. 63 (2013) p. 119. Power balance (2)
Pel=200 MW, Qel=3.5 Pel=700 MW, Qel=6
Pel=60 MW, Qel=2 The figure curves are calculated for the following parameters:
st=0.01, mir=0.15, st=0.05, =0.8, =0.8 and E=150 keV
Dependence of parameters of plasma part of SM hybrid on background plasma temperature Measurements of magnetic surfaces in Uragan-2M with embedded mirror The magnetic surfaces structure of the Uragan-2M torsatron: mode k 0.24, -14 cm. The negative sign of the magnetic axis displacement indicates only that the magnetic axis is located on the inner half of the torus. Its location in the cross- section denoted by the symbol ‘+’.
Magnetic surfaces structures in Magnetic surfaces structure in Uragan- Uragan-2M when the toroidal 2M when the toroidal magnetic field coil magnetic field coil number 14 was number 8 was switched off. switched off. Drift surfaces calculated =0.8, A=0 =0.8, A=0.05 =0.8, A=0.1 =0.7, A=0.1 0.08 0.08 0.08 0.08
0.06 0.06 0.06 0.06
0.04 0.04 0.04 0.04
0.02 0.02 0.02 0.02
0 0
0
0
_ _
0 0 _
_ R
R 0 0
/ /
R
R
/
z z
/ z -0.02 -0.02 z -0.02 -0.02
-0.04 -0.04 -0.04 -0.04
-0.06 -0.06 -0.06 -0.06 -0.08 -0.08 -0.08 -0.08 0.88 0.9 0.92 0.94 0.96 0.98 0.88 0.9 0.92 0.94 0.96 0.98 0.88 0.9 0.92 0.94 0.96 0.98 R/R_0 R/R_0 0.88 0.9 0.92 0.94 0.96 0.98 R/R_0 R/R_0 =0.8, A=-0.05 =0.8, A=-0.1 =0.9, A=-0.1 In calculations the 0.08 0.08 0.08 0.06 0.06 0.06 normalized energy 0.04 0.04 0.04
and electric 0.02 0.02 0.02
0
0 0
_ 0
_ _
R 0 0
/
R
R
z
/
/ z potential A are z -0.02 -0.02 -0.02 varied -0.04 -0.04 -0.04
-0.06 -0.06 -0.06 -0.08 -0.08 -0.08 0.88 0.9 0.92 0.94 0.96 0.98 R/R_0 0.88 0.9 0.92 0.94 0.96 0.98 0.88 0.9 0.92 0.94 0.96 0.98 R/R_0 R/R_0 Heavy ion beam probe
General view of HIBP system at Uragan-2M torsatron with beam control and data acquisition system Heavy ion beam probe (2)
• A system of plasma diagnostics using a beam of heavy ions had been put into operation on torsatron Uragan-2M. In experiments for the probe beam launching through a magnetic field torsatron (0.39 0.4T), the primary beam of cesium ions with an energy of 17 80 keV and a current of 10 mA 150 was used.
• Registration of doubly ionized beam of cesium ions had been made for the primary beam at an energy of 80 keV and a current of 100 mA.
• The primary beam with an energy of 17 20 keV (current 10 mA) had been launched through a magnetic field of the torsatron to the analyzer.
Studies on fusion reactor materials
QSPA Kh-50 device
W~ 4 MJ
Uc=15kV Id~0.7 MA =0.25 ms 2 W= 1-30 MJ/m E~0.5-0.9 keV
Bext≤0.7T
Vacuum chamber: L=10m =1.5m
QSPA plasma parameters are relevant to the ITER high heat loads (typical for disruptions and ELMs) to the divertor plates. Plasma-surface interaction and W erosion in 3-D geometry (brush and castellated targets)
The damage of surface, mechanisms of solid/liquid particle ejection for different parts of castellated targets exposed to QSPA plasma streams has been studied in the course of increasing number of pulses.
It is shown that melt dynamics at the structure edges, droplet splashing and molten bridges through the slits are determining processes in macroscopic erosion of castellated surface structures.
42 NATIONAL SCIENCE CENTER "KHARKOV INSTITUTE OF PHYSICS AND TECHNOLOGY" INSTITUTE OF PLASMA PHYSICS Collaboration with KIT (Germany) in validation of numerical models
Plasma stream
VPl
Vm Melt layer
W-brush
3D version of the code MEMOS was tested and is available now
Simulation of K-H Instability wavelengths Dependence of the wave length of the KH wave with maximum growth rate on plasma density for different plasma velocities along the surface NATIONAL SCIENCE CENTER "KHARKOV INSTITUTE OF PHYSICS AND TECHNOLOGY" INSTITUTE OF PLASMA PHYSICS
Dust generation mechanisms from W surface in ITER relevant conditions have been studied with QSPA Kh-50 Several mechanisms of dust generation under the transient energy loads to the tungsten surfaces have been recognized and identified : - Dust particles with sizes up to tens m could be ejected from the surface due to the cracking development and major cracks bifurcation. This mechanism would be important for first impacts when crack mesh is formed -Melting of surface and development of fine meshes of cracks along the grain boundaries are accompanied by resolidified bridges formation through the fine cracks in the course of melt motion and capillary effects. Such bridges produce nm-sized droplets and dust. -Modification of tungsten after the repetitive plasma pulses with development of ordered submicron cellular structures are may contribute significantly to the droplets and dust generation. -Melting of crack edges (both primary cracks and mickro-craks) is also the droplets source even with exposures below the melting threshold
Majority of generated small droplets and dust particles are deposited back to the surface by plasma pressure. This result is confirmed by plasma parameters measurements in front of the surface. In this sense the produced melt losses are quite small, the eroded mass is remained on the surface. However this is a source dust, that is able to migrate on the surface and it may retain the hydrogen isotopes.
QSPA-M concept A new QSPA-M device with magnetized plasma source
First plasma in the injection section
46 • New generation QSPA operates in external B field up to 2 T. • It is compact but more powerful. • It allows possibility to combine steady-state and pulsed loads in one testbad facility, using plasma of several kinds of ions (H,He) . • Also it offers new range of plasma parameters in QSPA plasma stream, that could not be reached before
47 NATIONAL SCIENCE CENTER "KHARKOV INSTITUTE OF PHYSICS AND TECHNOLOGY" INSTITUTE OF PLASMA PHYSICS First mirrors of ITER diagnostic systems. For more than 15 years, the quite broad program on simulation of behavior of in-vessel mirrors needed for many diagnostics in ITER is provided in group headed by Dr. V.S.Voitsenya. Investigations were carried out in the frame of cooperation of IPP NSC KIPT with NIFS, Cadarache, Garching, Juelich, and Basel University.
It was shown that in the case
when the surface sputtering by CXA prevails over deposition of contaminants, the first mirrors have to be fabricated from single crystals or as metal film on the Dependence of mono- and poly-crystal surface metal substrate. Reflectance for samples exposed in plasma with wide spectrum of ion energy.
48 Surface of polycrystalline tungsten after sputtering of 4 mkm layer
Grain orientation and surface Grain orientation (EBSD) by EBSD and confocal laser scanning microscope Significant difference in sputtering rate of granes with different orientation.
Δz= 1.5 µm
Δz= 1.5 µm Theoretical studies
• Plasma transport in stellarator, magnetic perturbations in tokamak plasma (V.V. Nemov, S.V. Kasilov in collaboration with TU-Graz, Austria); • Electron cyclotron heating (S.N. Pavlov in collaboration with CIEMAT, Spain); • Runaway electrons at tokamak (I.M. Pankratov in collaboration with IPP Hefei, China); • ICWC and RF plasma production modeling (V.E. Moiseenko and Yu.S. Kulyk in collaboration with LPP RMA, Belgium); • Particle motion in magnetic fields (V.E. Moiseenko in collaboration with Uppsala University, Sweden).
NATIONAL SCIENCE CENTER "KHARKOV INSTITUTE OF PHYSICS AND TECHNOLOGY" INSTITUTE OF PLASMA PHYSICS
Collaborations of IPP Max-Planck-Institut für Plasmaphysik, EURATOM Association, Germany University of Toronto Institute for Aerospace Studies, Toronto, ON, Canada University of Science and Technology Beijing, Beijing, China Hydrogen Isotope Research Center, University of Toyama, Japan Ångström Laboratory, Uppsala University, Uppsala, Sweden Laboratory for Plasma Physics - ERM/KMS, Brussels, Belgium CIEMAT , Madrid, Spain KIT , Karlsruhe, Germany FZJ, Julich, Germany PU, Purdue, USA National Centre for Nuclear Research, Poland IPPLM, Poland IPP, Czech Rep. Graz Un.. Austria Institut "Jozef Stefan", Ljubljana, Slovenia NIFS, Japan NATIONAL SCIENCE CENTER "KHARKOV INSTITUTE OF PHYSICS AND TECHNOLOGY" INSTITUTE OF PLASMA PHYSICS Summary
Some examples of fusion related activity in IPP NSC KIPT are presented.
Involvement of research infrastructure of IPP ( Stellarators U-3M and U-2M, QSPA Kh-50, new generation QSPA-M, number of small experimental stands, available diagnostics) and its highly qualified staff to the Eurofusion activity within Horison-2020 could be mutually benefitial and bringing new developments in fusion science and technology.
Support of fusion and plasma activity through joint STCU-NASU projects is launched (STCU project #6057 at IPP). Partner project mechanism of STCU may be used.
Existing international scientific collaboration of IPP with EU plasma centers in the field of plasma physics and controlled fusion and recently established research program of NASU on plasma physics (2 research projects in IPP) could be further base more ambitious joint research projects.
53 NATIONAL SCIENCE CENTER "KHARKOV INSTITUTE OF PHYSICS AND TECHNOLOGY" INSTITUTE OF PLASMA PHYSICS
Дякую за увагу!
54 Thank you!