Plasma Behavior with Hydrogen Supersonic Molecular Beam and Cluster Jet Injection in the HL-2A Tokamak

Similar documents
Characteristics of hydrogen supersonic cluster beam generated by a Laval nozzle

Corresponding Authors s address:

Disruption mitigation in ITER

Divertor Heat Flux Reduction and Detachment in NSTX

Formation of High-b ECH Plasma and Inward Particle Diffusion in RT-1

Noninductive Formation of Spherical Tokamak at 7 Times the Plasma Cutoff Density by Electron Bernstein Wave Heating and Current Drive on LATE

Abstract. Introduction TH/P3-2. contact of main author:

TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D

Modelling of JT-60U Detached Divertor Plasma using SONIC code

Flow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes

Alcator C-Mod. Particle Transport in the Scrape-off Layer and Relationship to Discharge Density Limit in Alcator C-Mod

Study of Current drive efficiency and its correlation with photon temperature in the HT-7 tokomak

1 EX/P6-5 Analysis of Pedestal Characteristics in JT-60U H-mode Plasmas Based on Monte-Carlo Neutral Transport Simulation

Highlights from (3D) Modeling of Tokamak Disruptions

Some Notes on the Window Frame Method for Assessing the Magnitude and Nature of Plasma-Wall Contact

Driving Mechanism of SOL Plasma Flow and Effects on the Divertor Performance in JT-60U

ELM Mitigation by Supersonic Molecular Beam Injection: KSTAR and HL-2A Experiments and Theory

Results From Initial Snowflake Divertor Physics Studies on DIII-D

GA A22443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D

Scaling of divertor heat flux profile widths in DIII-D

Alcator C-Mod. Particle Transport in the Alcator C-Mod Scrape-off Layer

Development of a New Gas Puff Imaging Diagnostic on the HL-2A Tokamak

1 EX/P5-24. Observation of a Natural Particle Transport Barrier in HL-2A Tokamak

Bolometry. H. Kroegler Assciazione Euratom-ENEA sulla Fusione, Frascati (Italy)

Phase ramping and modulation of reflectometer signals

Simulation of Plasma Flow in the DIII-D Tokamak

Study of B +1, B +4 and B +5 impurity poloidal rotation in Alcator C-Mod plasmas for 0.75 ρ 1.0.

Cross-Field Plasma Transport and Main Chamber Recycling in Diverted Plasmas on Alcator C-Mod

Divertor Requirements and Performance in ITER

Cluster fusion in a high magnetic field

Progress of Confinement Physics Study in Compact Helical System

GA A23411 COMPARISON OF LANGMUIR PROBE AND THOMSON SCATTERING MEASUREMENTS IN DIII D

Disruption Mitigation on Tore Supra

Minimal Model Study for ELM Control by Supersonic Molecular Beam Injection and Pellet Injection

STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-60U

HFS PELLET REFUELING FOR HIGH DENSITY TOKAMAK OPERATION

Physics of the detached radiative divertor regime in DIII-D

Analyses of Visible Images of the Plasma Periphery Observed with Tangentially Viewing CCD Cameras in the Large Helical Device

Direct drive by cyclotron heating can explain spontaneous rotation in tokamaks

ITER operation. Ben Dudson. 14 th March Department of Physics, University of York, Heslington, York YO10 5DD, UK

Recent Development of LHD Experiment. O.Motojima for the LHD team National Institute for Fusion Science

Scaling of divertor heat flux profile widths in DIII-D

Parallel transport and profile of boundary plasma with a low recycling wall

On Dust Particle Dynamics in Tokamak Edge Plasma

Visualization of Xe and Sn Atoms Generated from Laser-Produced Plasma for EUV Light Source

First plasma operation of Wendelstein 7-X

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

Lower Hybrid Current Drive Experiments on Alcator C-Mod: Comparison with Theory and Simulation

Confinement Studies during LHCD and LHW Ion Heating on HL-1M

Recent results on non-inductive startup of highly overdense ST plasma by electron Bernstein wave on LATE

Behavior of Compact Toroid Injected into the External Magnetic Field

ARTICLES PLASMA DETACHMENT IN JET MARK I DIVERTOR EXPERIMENTS

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

EXD/P3-13. Dependences of the divertor and midplane heat flux widths in NSTX

Bifurcation-Like Behavior of Electrostatic Potential in LHD )

Upper Hybrid Resonance Backscattering Enhanced Doppler Effect and Plasma Rotation Diagnostics at FT-2 Tokamak

Characteristics of the H-mode H and Extrapolation to ITER

ITER Divertor Plasma Modelling with Consistent Core-Edge Parameters

Volume Recombination and Detachment in JET Divertor Plasmas

Reduction of Turbulence and Transport in the Alcator C-Mod Tokamak by Dilution of Deuterium Ions with Nitrogen and Neon Injection

Confinement of toroidal non-neutral plasma

Preliminary experiment of plasma current startup by ECR wave on SUNIST spherical tokamak

1. Motivation power exhaust in JT-60SA tokamak. 2. Tool COREDIV code. 3. Operational scenarios of JT-60SA. 4. Results. 5.

Effect of the MHD Perturbations on Runaway Beam Formation during Disruptions in the T-10 Tokamak

Physics of fusion power. Lecture 14: Anomalous transport / ITER

MAGNETIC NOZZLE PLASMA EXHAUST SIMULATION FOR THE VASIMR ADVANCED PROPULSION CONCEPT

Overview of Experimental Results on HL-2A

Observations of Counter-Current Toroidal Rotation in Alcator C-Mod LHCD Plasmas

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

Cesium Dynamics and H - Density in the Extended Boundary Layer of Negative Hydrogen Ion Sources for Fusion

DIII-D TOKAMAK MODELING OF THE RECYCLING PARTICLE FLUX AND ELECTRON PARTICLE TRANSPORT IN THE

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

UPGRADED CALIBRATIONS OF THE THOMSON SYSTEM AT DIII D

Density Limit and Cross-Field Edge Transport Scaling in Alcator C-Mod

Estimating the plasma flow in a recombining plasma from

Measurement of lower hybrid waves using microwave scattering technique in Alcator C-Mod

INTRODUCTION. As shown in Figure 1a, the phenomena of lightningmesosphere-ionosphere

Predictive Study on High Performance Modes of Operation in HL-2A 1

Steady State and Transient Power Handling in JET

The Larmor Formula (Chapters 18-19)

GA A26123 PARTICLE, HEAT, AND SHEATH POWER TRANSMISSION FACTOR PROFILES DURING ELM SUPPRESSION EXPERIMENTS ON DIII-D

Effect of non-axisymmetric magnetic perturbations on divertor heat and particle flux profiles

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

1 EX/P7-35. Spectroscopic Studies on GLAST-III Varying the Inductance and Charging Voltage of Vertical Field Coils

Drift-Driven and Transport-Driven Plasma Flow Components in the Alcator C-Mod Boundary Layer

ITER A/M/PMI Data Requirements and Management Strategy

On the physics of shear flows in 3D geometry

D.J. Schlossberg, D.J. Battaglia, M.W. Bongard, R.J. Fonck, A.J. Redd. University of Wisconsin - Madison 1500 Engineering Drive Madison, WI 53706

Internal magnetic field measurement in tokamak plasmas using a Zeeman polarimeter

Laser heating of noble gas droplet sprays: EUV source efficiency considerations

1 EX/P4-8. Hydrogen Concentration of Co-deposited Carbon Films Produced in the Vicinity of Local Island Divertor in Large Helical Device

The Plasma Phase. Chapter 1. An experiment - measure and understand transport processes in a plasma. Chapter 2. An introduction to plasma physics

Relating the L-H Power Threshold Scaling to Edge Turbulence Dynamics

Axial symmetric open magnetic traps with depressed transversal losses of plasmas

Studies of H Mode Plasmas Produced Directly by Pellet Injection in DIII D

Integrated Modeling of Fast Ignition Experiments

PIC/MCC Simulation of Radio Frequency Hollow Cathode Discharge in Nitrogen

Diagnostics for Burning Plasma Physics Studies: A Status Report.

Overview of Recent Results from Alcator C-Mod including Applications to ITER Scenarios

GA A23996 DISRUPTION MITIGATION WITH HIGH-PRESSURE NOBLE GAS INJECTION

Transcription:

1 EX/P3-21 Plasma Behavior with Hydrogen Supersonic Molecular Beam and Cluster Jet Injection in the HL-2A Tokamak L.H Yao 1), B.B. Feng 1), C.Y. Chen 1), Z.B. Shi 1), B.S. Yuan 1), W,W. Xiao 1), Y. Zhou 1), H.J. Sun 1), J. Lu 1), X.R. Duan 1), Y.D. Pan 1), W.Y. Hong 1), W. Li 1), H. Ran 1), G.Q. Ni 2), H.Y. Lu 2), X.T. Ding 1), and Y Liu 1) 1) Southwestern Institute of Physics, Chengdu, China 2) Shanghai Institute of Optics and Fine Mechanics, Shanghai, China e-mail contact of main author: yaolh@swip.ac.cn Abstract. The experimental results of low pressure supersonic molecular beam injection (SMBI) into the HL-2A plasma indicated that during the period of SMB pulse injection the power density convected at the divertor target plate surfaces was 0.4 times of that before or after the beam injection. The clusters are produced at nitrogen temperature in a supersonic adiabatic expansion of moderate pressure hydrogen gases into vacuum through a Laval nozzle. The averaged cluster size was measured by Rayleigh scattering as large as hundreds atoms. Multifold diagnostics for the cluster jet injection (CJI) experiments have given a coincident evidence that there was a terminal area where a great deal particles from the clusters deposited at, rather than the clusters uniformly ablating along the injection path. A SMB with large clusters, which are like micro-pellets, was of benefit for deeper fuelling and the fuelling efficiency is distinctly better than that of the room temperature SMBI. Another important effect of the CJI or the high pressure SMBI was that the runaway electrons were cooled down to thermal velocity due to a combination of collision and radiative stopping in such a massive fuelling. So the new fuelling technique may become a good treatment to mitigate fast plasma shutdowns and disruptions. 1. Introduction After more than ten years of practice, SMBI has been developed to become a useful fuelling method that is already considered to be an improvement over conventional gas puffing (GP). The high-pressure (more than 1 MPa) multi-pulse SMBI takes a further step towards high performance discharge of the plasma for the onset of injected particle clustering [1]. There is no rigorous theory to predict cluster formation in a free jet expansion. However, the onset of * clustering can be described by an empirical scaling parameter Γ referred to as the Hagena * parameter [2], clustering generally begins for Γ > 100-300. In the HL-1M experiment, the * Hagena parameter Γ is above 200, so cluster onset may occur. The HL-2A tokamak is the first tokamak with diverters in China. The main parameters of HL-2A are R = 1.65 m, a = 0.4 m, B t = 2.8 T and I p = 0.48 MA. The divertor of the machine is characterized with two closed divertor chambers, but now it is operated with lower single null configuration [3]. Large hydrogen cluster (>100 atoms) can be produced at low temperature gas. The experiment of hydrogen CJI into the HL-2A plasma was carried out and the particle injection depth and the fuelling efficiency were distinctly better than that of the room temperature SMBI. 1. Experimental set-up of SMBI system in HL-2A The experimental set-up of SMBI system in HL-2A and the detail structure of the molecular beam valve with cooling trap are shown in FIG. 1. The valve used for producing supersonic molecular beam is a solenoid driven pulsed valve S99 with a 0.2 mm diameter cylindrical.

2 EX/P3-21 The distance between the nozzle of the valve and the edge plasma is about 1.28 m. The penetration characteristics of SMBI were measured by means of the tangential H photodiode detection array as shown in FIG. 2. Two arrays of Langmuir probes are installed on the inner- and outer- target plates of the lower divertor, respectively [4]. Separatrix Target plate H Array 1 SMB Valve LNt LN 2 output H2 inlet LN 2 inlet CCD Camera Turb Pump Lower divertor H Array 2 FIG. 1. Supersonic molecular beam injection system in the HL-2A Tokamak 2. The behavior of the recycling flux for low pressure hydrogen SMBI into the HL-2A limiter configuration One crucial point is the behavior of the recycling fluxes from the vessel wall during the beam injection. FIG. 3 shows the time traces of the H detectors, of which one marked as Ha-046(v) is H emission intensity from tangential 46th channel. I_Ha_w(v) and I_Ha_s(v) is adjacent to the beam export, and the two others I_Ha_n(v) and I_Ha_e(v) represent the north and the east azimuth H emission intensity, respectively. Directly after the pulse beam injection, the H intensity drops at a distance from the beam injection location of I_Ha_n(v) and I_Ha_e(v), and is recovered after 30 ms to the value before the injection. This indicates a transient reduction of the recycling fluxes during the beam injection. It is supported by the heat radiation detected from the Bolometer (BOL_08(v)) and the neutral gas manometer measurement which signal signed as Ph2p, by both of the detectors a reduction of heat emission and the neutral pressure after the beam injection is registered, respectively. 3. The effect of low pressure hydrogen SMBI on the HL-2A divertor A train of ten pulses of hydrogen molecular beam produce at low pressure 0.2 ~ 0.3 MPa, each pulse duration 10 ms and pulse period 30 ms, was injected at the mid-plane of the HL-2A torus and along the major radius from t = 200 ms and the diveretor function was

3 EX/P3-21 started up at t = 240 ms. After t = 240 ms the fuelling particles from the later eight molecular beam pulses not only can enter into the main plasma, but also the divertor chamber. FIG. 2. the scheme of the MBI system and the tangential Ha detection system, total number of the Ha channels is 46, distance between adjacent channels is 5mm along the radius. FIG. 3. Reduction of H intensity (except the beam injection location), heat emission and neutral pressure after SMBI. FIG. 4. Behavior of ten pulses of SMBI into HL-2A Plasma. The fuelling characteristics of the SMBI into HL-2A plasma with and without lower closed divertor configuration for shot 2987 are as shown in FIG. 4. During the periods of SMB pulse injection the electron density near by the neutralized plates of the divertor increases an order of magnitude than that in the interval of the beam pulses under the divertor configuration. The electron density on the inner and outer target plate location ned div I and ned div O varies linearly with density n ea in SOL, respectively, i.e. ned div I ned div O 1.5 n ea. On the other hand, the electron temperature on the target plate locations also varies linearly with the upstream temperature, Ted div I is approximately equal 2 of T 3 ed in SOL, as shown in FIG. 4. During the period of SMBI fuelling, the electron temperature on the target plate locations is less than 5 ev. So the HL-2A lower divertor was operated at the linear regime. There is a boundary condition that is imposed on the conduction of heat in the SOL, which determines the power density q t that can be

4 EX/P3-21 convected through the electrostatic sheath at the target plate surface [5]. The ratio of power density q t, during the SMBI period, to q t, before or after the beam injection equals 0.4. That is, during SMBI the heat load on the target plate surface is just 0.4 times of that before or after the beam injection. So SMBI may be as a useful fuelling method to decrease the heat load on the neutralizer plates and to make a safe circumstance for the divertor operation. The particle confinement time τ p increased by a factor of two during the SMBI may incidentally obtained by Staib s model [6] from the measurements. 4. SMBI as a good perturbation source for studying particle transport Pulsed molecular beam has high instantaneous intensity, higher and approximately uniform speed than normal GP, small spread of velocity with narrow angular distribution. So a train of SMB pulses is used for a particle perturbation source to study the particle transport. A microwave reflectometer with scanning frequency range of 26 GHz to 40 GHz, which corresponding to the density 19 3 range (0.8-2) 10 m, has been used to measure the electron density profiles [7, 8]. The temporal resolution and spatial resolution are 1 ms and 1 cm, respectively. The pulse duration is 5 ms and the period of the pulse is 55ms. After the fast fourier treatment (FFT) analysis, the amplitude and the phase profiles of the first and second harmonics can be obtained, respectively, as shown in FIG.5. The FIG. 5. The amplitude profiles at maximum amplitude and the minimum phase in the first, second harmonic in shot 3874, profiles are nearly in the same radial position. The (a) first harmonic, (b) second minimum phase of the second harmonic are located harmonic. at the same position, r 28 cm, which means that the pulse perturbation source is mainly located at this position. The particle diffusion 2 coefficient D, which can be determined by D = ω / 2( Φ'), is equal to 0.5 1.5 m 2 / s at the range of r = 26 cm to 30 cm. 5. Rayleigh scattering experiment for the measurement of hydrogen cluster The hydrogen clusters were produced by the supersonic adiabatic expansion of moderate backing pressure gases into vacuum through a Series 99 valve with a nozzle of 0.5 mm diameter, the temperature of the gas source composed of the valve and its nozzle was cooled to 80K. The Rayleigh scattering method was employed to measure the hydrogen cluster size [9,10,11]. A 532 nm pulsed laser beam was introduced into the vacuum chamber to intersect the hydrogen plume at a right angle. A photomultiplier, which was arranged in the direction perpendicular both to the cluster jet and to the incident laser beam, was used to amplify the scattered light from the hydrogen clusters. In the present experiments, Rayleigh scattered light 1.4 signal S RS scales with P 0 as S RS P 0. The average cluster size N c also is a function 0.4 of P 0, and varies as N c P 0. Averagely there is about 250 hydrogen atoms within a cluster at the backing pressure of 1.0 MPa in this measurements.

5 EX/P3-21 6. The penetration depth of the CJ and SMB There are two diagnostic methods used to reveal the penetration depth of the CJ and SMB: one of them is the tangential H detection array that shows the trace-ray of the injected particles and the other is dt e /dt measured by ECE. The maximum point of dt e /dt at the radial position corresponds to the center of the concentrating area for the injected particles. As for the GP particles of shot 4049, they can hardly penetrate into the plasma confinement region, the profile of dt e /dt appears in flatten and the maximum point of dt e /dt was at the outmost location in the plasma column as shown in FIG. 6. The penetration depth of CJI for shot 4413 with 80 K hydrogen is more than that of SMBI for 4512 with room temperature at the same backing pressure 1.8 MPa. The particles from PI of shot 4050 can deposite at the plasma center. The measurement precision is limited by the ECE scanning time of 4 ms. FIG. 7 shows the distributions of intensities for the tangential H emission detected by the array for shot 4413 and shot 4512, respectively. The top point of the H profile versus radius corresponds to the area where the injecting particles mainly deposited at. If the particles concentrate in a very small area, then the distribution of the maximum value of H emission will be sharp and the measurement precision of the injection depth will be better. The typical example is the profile of shot 4413 in FIG. 7. In contract to that, the injecting effects for shot 4512 with room temperature gas, either the measurement precision or the injection depth, were not perfect, the injected particles may concentrate in such a large area, so as can hardly find a tip. A comparison of penetration depth for both of CJ and SMB under the similar discharge condition is listed in the TABLE 1. FIG. 6. Comparison of penetration depth for four different fuelling methods. PI: Shot 4050;CJI: Shot 4413, LN 2 temperature gas, 1.8 MPa; SMBI: Shot 4512, room temperature gas, 1.8 MPa; GP: Shot 4049, room temperature gas, 0.2 MPa. FIG. 7. Profiles of H emission measured by the tangential detector array for shot 4413 and 4512 TABLE 1: COMPARISON OF INJECTION DEPTH FOR CJ AND SMB Diagnostics method Shot 4413 (LN 2 Shot 4512 (room temperature gas) temperature gas) Tangential H detector array r = 6 cm R = 26-28 cm dte/dt detected by ECE r = 18 cm R = 21 cm

6 EX/P3-21 7. The fuelling efficiency of cryogenically cooled gas cluster jet In the present experiment, the fuelling efficiency for CJI is roughly about 60% under normal HL-2A wall condition, because it is strongly dependent on the plasma parameters and wall condition. A comparison of fuelling effect was shown in FIGS. 8a and 8b between CJI of shot 4413 with 80 K hydrogen and SMBI of shot 4512 with room temperature one under approximate discharge parameters. The backing pressure for the both shots was 1.8 MPa and two pulses for each shot. It is in evidence that the cluster jet fuelling effect is strongly dependent on the gas temperature, the density increment for shot 4413 with CJI is twice of that for shot 4512 with SMBI. Even if the velocity for the cluster jet is just one half of that for the beam, but the averaged size of the cluster was as large as hundreds atoms. Apparently, the size of cluster making a contribution to fuelling effect is more important than its velocity. FIG. 8a. Cryogenically cooled gas CJI into HL-2A plasma with divertor configuration for shot 4413, the plasma density increases 2.2 10 19 m -3 from 1.52 to 3.72 10 19 m -3. FIG. 8b. Room temperature gas SMBI into HL-2A plasma with divertor configuration for shot 4512, the plasma density increases 1.2 10 19 m -3 from 1.61 to 2.81 10 19 m -3. 8. Variation of ion temperature and radiation power during and after CJI or high pressure SMBI As is shown in FIG. 9, the ion temperature sharply increases during the high-pressure SMBI of 4027 and the CJI of 4413 into the HL-2A plasma, and the plasma radiation power rapidly increases as well. The variations of ion temperature were resulted from a great deal increment of the counting rate of higher energy hydrogen atom at the range of 5 to 7 kev measured by the charge-exchange neutral particle analyzer. An receivable interpretation for this phenomena is due to the hydrogen particles or clusters deeply injecting into the high temperature confinement region of HL-2A and in which a great deal particles depositing in, and resulting in the yield of charge-exchange higher energy hydrogen atom strongly increased. Whereas the counting rate for the charge-exchange neutral particles are not linear increasing along the injecting path, that means the injecting clusters deposited slightly on the way. In the high pressure gas injection experiments, it was found that the energy of the runaway electrons was limited almost independently of the used gas species [12]. The stopping powers for runaway electrons in hydrogen gas are shown in FIG. 10 [13]. In such a massive injection, if the average injected neutral particle density N m 2 10 17 atoms / m 3, it is about 0.01 order of magnitude of the average electron density of HL-2A, then the critical field for runaway E = 0.094 V / m. Normally the electric field E for ohmic discharge in the HL-2A c

7 EX/P3-21 1000 800 T i (ev) 600 400 200 Shot 4027 0 200 400 600 800 1000 1200 1400 t(ms) 1000 800 FIG. 10. Stopping powers for runaway electrons in hydrogen gas. The ohmic electric field driving force F = e E. W c1 in the collision dominated region and W c2 in the radiative dominated region. The electrons return journey between W c1 and W c2. T i (ev) 600 400 200 Shot 4413 0 300 450 600 750 900 1050 t(ms) FIG. 9. Ion temperature sharply increases during the high-pressure SMBI of shot 4027 and CJI of shot 4413. Shot 4027: Gas pressure 3.0 MPa, three pulses. Shot 4413: Gas pressure 1.8 MPa, double jets. FIG. 11. Radiation behavior of CJI into HL-2A plasma at t = 800 ms, the peaking profile of radiation power appeared in asymmetry at z /a = ± 0.75 from t = 818.8 to 819.6 ms. Then the peaking returns to z = 0 and z /a = -0.75 at t = 821.2 ms. torus is equal to 0.11 V / m. The ratio E/Ec 1 and the radiation stopping power W c2 decreases greatly. The effect of the mass gas injection is that even already existing runaways are cooled down by the strong radiation as shown in FIG. 11 and can not trigger the avalanche process. So this fuelling method not only reduce the energy of runaway electrons, but may become a tool to mitigate their effects during fast plasma shutdowns and disruptions. 9. Conclusion and discussion The study of plasma behavior with room-temperature gas SMBI fuelling was carried out in the HL-2A experiments with the closed divertor. The fuelling characteristics of SMBI in HL-1M, such as enhancing the penetration depth and fuelling efficiency, reducing surface adsorption of the injected particles and the particle recycling, were reappearance in the HL-2A

8 EX/P3-21 plasma. In addition, the heat load on the target plate surface is just 0.4 times of that before or after the beam injection, and the particle confinement time τ p increased by two times The hydrogen gas at room temperature can not form large cluster ( say, more 100 atoms) by the adiabatic expansion even if the backing pressure is as high as 4 MPa or more. It has been confirmed that the hydrogen clusters produced at nitrogen temperature in the process of supersonic adiabatic expansion were measured by Rayleigh scattering. The pulsed MBI with large hydrogen clusters is a effective fuelling method for deeper injection. The diagnostics used for CJI experiments, including the tangential H emission detector array, the ECE measurement, the scanning microwave reflectometry and the charge-exchange neutral particle analyzer, gave coincident evidence that the injection particles do not uniformly deposited along the injecting path in the plasma and there is a terminal area where a great deal particles deposited at. The plasma behavior with pulse hydrogen CJI was somewhat similar to that of PI. The idea mentioned at previous work [14], a supersonic molecular beam with clusters, which are like micro-pellets, will be of benefit for deeper fuelling. has being put into practice in HL-2A. Such a simple technology for producing hydrogen micro-pellets is a great high light for the new fuelling method. In addition, the effect of the CJI or the high pressure SMBI is that even already existing runaways are cooled down and can not trigger the avalanche process. So this fuelling method may become a tool to mitigate their effects during fast plasma shutdowns and disruptions. Acknowledgments This work was supported by the National Natural Science Foundation of China under Grant No19775011, 10075016 and 10475024. References [1] Yao Lianghua, et al 2004 Nucl. Fusin 44 420 [2] Smith R.A., Ditmire T. and Tish W.G. 1988 Rev. Sci. Instrum. 69 3798 [3] Liu Y. et al 2005 Nucl. Fusin 45 S239 [4] Yan L.W. et al 2005 Plasma Science & Technology 7 2797 [5] Pitcher C S and Stangeby P C, et al 1997 Plasma Phys. Control Fusion 39 779 [6] Staib P. et al 1982 J. Nucl. Mat. 111&112 109 [7] Xiao W.W. et al 2006 Plasma Science & Technology 8 133 [8] Ding X.T. et al 2006 Rev. Sci. Instrum. (To be published) [9] Ditmire T. et al 1996 Phys. Rev. A 53 3379 [10] Ditmire T. et al 1998 Phys. Rev. A 57 369 [11] Liu B.C. et al 2002 Chin. Phys. Lett. 19 659 [12] Bakhtiari, et al 2005 Phys. Rev. Lett. 94 215003 [13] Berger M.J., Cousey J.S. and Zucker M.A. EATAR: Computer Program for Calculating Stopping-Power and Range Tables for Electrons(Version 1.2.2) (National Institute 0f Standards and Technology, Gaithersburg, MD. 2003), http://physics,nist.gov/star. [14] Yao Lianghua, et al 2001 Nucl. Fusin 41 817