Volume Recombination and Detachment in JET Divertor Plasmas

Similar documents
ARTICLES PLASMA DETACHMENT IN JET MARK I DIVERTOR EXPERIMENTS

Power Deposition Measurements in Deuterium and Helium Discharges in JET MKIIGB Divertor by IR-Thermography

Physics of the detached radiative divertor regime in DIII-D

Impurity accumulation in the main plasma and radiation processes in the divetor plasma of JT-60U

Divertor Heat Flux Reduction and Detachment in NSTX

Deuterium Balmer/Stark spectroscopy and impurity profiles: first results from mirror-link divertor spectroscopy system on the JET ITER-like wall

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

Scaling of divertor heat flux profile widths in DIII-D

Plasma-edge Gradients in L-mode and ELM-free H-mode JET Plasmas

Estimating the plasma flow in a recombining plasma from

EFDA European Fusion Development Agreement - Close Support Unit - Garching

Results From Initial Snowflake Divertor Physics Studies on DIII-D

Power Balance and Scaling of the Radiated Power in the Divertor and Main Plasma of Alcator C-Mod

Modelling of Carbon Erosion and Deposition in the Divertor of JET

L-Mode and Inter-ELM Divertor Particle and Heat Flux Width Scaling on MAST

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

Divertor physics research on Alcator C-Mod. B. Lipschultz, B. LaBombard, J.L. Terry, C. Boswell, I.H. Hutchinson

Detachment Dynamics on the TCV Tokamak

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

Local Plasma Parameters and H-Mode Threshold in Alcator C-Mod

Scaling of divertor heat flux profile widths in DIII-D

Recent results on high-triangularity H-mode studies in JET-ILW

Scaling of divertor plasma effectiveness for reducing target-plate heat flux

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

THE ADVANCED TOKAMAK DIVERTOR

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

Confinement and edge studies towards low ρ* and ν* at JET

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

Role of Magnetic Configuration and Heating Power in ITB Formation in JET.

IMPLICATIONS OF WALL RECYCLING AND CARBON SOURCE LOCATIONS ON CORE PLASMA FUELING AND IMPURITY CONTENT IN DIII-D

Plasma Spectroscopy Inferences from Line Emission

Observation of Alpha Heating in JET DT Plasmas

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

L-mode radiative plasma edge studies for model validation in ASDEX Upgrade and JET

Detached Divertor Operation in DIII-D Helium Plasmas

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

Studies in JET Divertors of Varied Geometry I: Non Seeded Plasma Operation

Long Distance Coupling of Lower Hybrid Waves in JET using Gas Feed

GA A22863 PLASMA PRESSURE AND FLOWS DURING DIVERTOR DETACHMENT

Two-dimensional structure of the detached recombining helium plasma associated with molecular activated recombination

SCALING AND PROFILES OF HEAT FLUX DURING PARTIAL DETACHMENT IN DIN-D

DIVIMP simulation of W transport in the SOL of JET H-mode plasmas

Improved Plasma Confinement by Ion Bernstein Waves (IBWs) Interacting with Ions in JET

GA A22443 STUDY OF H MODE THRESHOLD CONDITIONS IN DIII D

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

Multi-machine comparisons of divertor heat flux mitigation by radiative cooling with nitrogen

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

HIGH PERFORMANCE EXPERIMENTS IN JT-60U REVERSED SHEAR DISCHARGES

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

ITER Divertor Plasma Modelling with Consistent Core-Edge Parameters

Isotope Exchange in High Heat-flux Components of the JET Tritium Neutral Beam Injector

TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D

Plasma Radiation. Ø Free electrons Blackbody emission Bremsstrahlung

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

ONION-SKIN METHOD (OSM) ANALYSIS OF DIII D EDGE MEASUREMENTS

H-mode performance and pedestal studies with enhanced particle control on Alcator C-Mod

Partial detachment of high power discharges in ASDEX Upgrade

PSI meeting, Aachen Germany, May 2012

Divertor Requirements and Performance in ITER

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

Divertor power and particle fluxes between and during type-i ELMs in ASDEX Upgrade

Simulation of Plasma Flow in the DIII-D Tokamak

Phase ramping and modulation of reflectometer signals

Ion Cyclotron Emission from JET D-T Plasmas

Radiative type-iii ELMy H-mode in all-tungsten ASDEX Upgrade

Improved EDGE2D-EIRENE Simulations of JET ITER-like Wall L-mode Discharges Utilising Poloidal VUV/visible Spectral Emission Profiles

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

Power Balance Analysis of Wendelstein 7-X Plasmas Using Profile Diagnostics

ITER A/M/PMI Data Requirements and Management Strategy

Steady State and Transient Power Handling in JET

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

Electron energy distribution function in the divertor region of the COMPASS tokamak during neutral beam injection heating

Divertor Heat Load in ITER-Like Advanced Tokamak Scenarios on JET

Exhaust scenarios. Alberto Loarte. Plasma Operation Directorate ITER Organization. Route de Vinon sur Verdon, St Paul lez Durance, France

Introduction to the Diagnosis of Magnetically Confined Thermonuclear Plasma

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

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

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

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

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

Fusion Nuclear Science Facility (FNSF) Divertor Plans and Research Options

Effect of divertor nitrogen seeding on the power exhaust channel width in Alcator C-Mod

Progress of Confinement Physics Study in Compact Helical System

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

FAR SCRAPE-OFF LAYER AND NEAR WALL PLASMA STUDIES IN DIII D

Effect of Variation in Equilibrium Shape on ELMing H Mode Performance in DIII D Diverted Plasmas

Divertor Power Handling Assessment for Baseline Scenario Operation in JET in Preparation for the ILW

'Associazione Euratom-ENEA sulla Fusione, Frascati, Italy. To be published in the Proceedings of the 1 6 th IAEA Fusion Energy Conference.

GA A26119 MEASUREMENTS AND SIMULATIONS OF SCRAPE-OFF LAYER FLOWS IN THE DIII-D TOKAMAK

Impact of Carbon and Tungsten as Divertor Materials on the Scrape-off Layer Conditions in JET

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

Divertor Detachment on TCV

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

Improved Plasma Confinement by Ion Bernstein Waves (IBWs) Interacting with Ions in JET (Joint European Torus)

Impurity Seeding in ASDEX Upgrade Tokamak Modeled by COREDIV Code

Flux & Energy Dependence of Methane Production From Graphite Due to H + Impact

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

Helium-3 transport experiments in the scrape-off layer with the Alcator C-Mod omegatron ion mass spectrometer

Experimental results and modelling of ASDEX Upgrade partial detachment

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

Transcription:

JET CP(98)1 Volume Recombination and Detachment in JET Divertor Plasmas G M McCracken, R D Monk, A Meigs, L Horton, L C Ingesson, J Lingertat, G F Matthews, M G O Mullane, R Prentice, M F Stamp, P C Stangeby 1. JET Joint Undertaking, Abingdon, Oxfordshire, OX1 3EA, 1 University of Toronto, Institute for Aerospace Studies, M3H 5T6, Canada. 13

This document is intended for publication in the open literature. It is made available on the understanding that it may not be further circulated and extracts may not be published prior to publication of the original, without the consent of the Publications Officer, JET Joint Undertaking, Abingdon, Oxon, OX1 3EA, UK. Enquiries about Copyright and reproduction should be addressed to the Publications Officer, JET Joint Undertaking, Abingdon, Oxon, OX1 3EA.

ABSTRACT The spatial distribution of recombination has been studied in the detaching phases of L and H- mode discharges. Recombination is detected by the sudden increase in intensity of the high quantum number states of the Balmer series of hydrogen. In L-mode, detachment occurs completely and the radiation moves to a region near the x-point. In H-mode, detachment only occurs between ELMs. There is a marked decrease in the pedestal Te inside the separatrix and loss of confinement before detachment takes place. 1. INTRODUCTION. Volume recombination in hydrogenic plasmas has recently been shown, both experimentally and theoretically, to play an important role in plasma detachment from the target plates of diverted discharges [1,]. Experimental evidence of recombination has been obtained in JET from the increase in the ratio of the intensities of the Balmer series lines of excited hydrogen atoms, Dγ/Dα and Dδ/Dα [3]. The start of recombination is closely correlated, both spatially and temporally, with the onset of detachment. Detachment is generally defined here as when the ion current to the target, as determined by the Langmuir probes, does not increase with ne as expected []. Recombination enhances hydrogenic radiation and reduces the power flow to the target. It is also a clear indicator of very low plasma temperature, ~1 ev. In the present paper we have examined the spatial distribution of recombination in detail using a CCD camera with optical filters at the Dγ and Dα lines of the hydrogen Balmer series and have extended our discusssion to H-mode discharges. In ohmic and L-mode discharges with a density ramp, recombination occurs first at the inner target and then, near the density limit, it occurs at the outer target. At the outer target the Dγ/Dα and Dδ/Dα, ratios have been measured as a function of radial position. It is shown that in both L-mode and H-mode discharges recombination predominantly takes place close to the separatrix strike point.. DIAGNOSTICS Spectroscopically resolved data in the visible are available from integrated views of both the inner and outer JET divertor targets, measured simultaneously. Two spectrometers (KS3) are survey instruments and routinely monitor the deuterium Balmer series lines Dα, (656.7 nm), Dβ, (86.13 nm) and Dγ (3.5 nm) as well as impurity lines. A second pair of spectrometers (KT3A/B) have 1 spatial tracks across the outer target, each 13 mm wide. One (KT3B) covers the visible spectrum range, to 7 nm, with a resolution of.1 nm and can monitor Dβ, Dγ and Dδ (1.17 nm) simultaneously. The second (KT3A) also covers the near uv ( to 7 nm) with a resolution of.5 nm. KT3A has been used to measure the electron density using the Stark broadening of the high n states of the deuterium Balmer lines [5]. The spatial distribution across the inner and outer target of different spectroscopic lines is obtained, with 3 mm resolu- 15

tion at the target, from three CCD cameras with interference filters, (KL). Optical filters have been used to study the Dα and the Dγ lines, as well as the CII line at 657.8 nm, which allows.8 1. KL Flux camera us to look at the spatial distribution of the Dγ/ KS3I 1. KS3 Dα ratio in much more detail than in our earlier studies []. In addition to the spectroscopic Separatrix KT3B diagnostics there is a poloidal array of fixed 1. Langmuir probes (KYD) in the inner and outer KKD targets which are used to measure local ion saturation current and electron temperature. An 19 1.6 16 135 Outer interferometer (KKD) is used to measure the 11 1131 Inner 7 probes 83 probes (KYD) 1.8 line integral density across the outside divertor target fan just above the target. The lines of Major radius (m) Fig. 1. Poloidal cross section of JET showing the lines sight of these diagnostics are shown in Fig. 1. of sight of the spectroscopic diagnostics, the probes and In addition to the above diagnostics there the divertor interferometer. are three cameras with optical filters looking at Dα, Dγ and CII (658 nm) tangentially into the torus via an endoscope. At present the data is recorded on videotape and is uncalibrated but it allows the vertical height of the Dγ and Dα radiation to be assessed 3. RESULTS 3.1. Ohmic and L-mode discharges Ohmic and L-mode discharges, with density ramps obtained by gas puffing, have been studied routinely to assess the density limit under a range of different conditions [6]. The general behaviour of an L-mode discharge with MW of neutral beam heating and with the strike point on the horizontal target (Fig. 1) is shown in Fig.. As the density rises, first the inner target detaches and then, near the density limit, the outer target detaches. Detachment is first observed when the ion current stops increasing proportionally to ne, Fig. d. This is more clear cut in the case of the outer target than the inner one. There is an increase in the Height below midplane (m) Density (1 19 m 3 ) NB Power (MW) Density (1 18 m ) Flux (1 /s)...6.8 3. 3. 3.5 3..5. 1.5 Pulse No: 3387 a) 1 b) D γ / D α c) Inner Detach Divertor n e dl d) Ion flux n e Inner target Inner target P NB 13 1 15 16 17 18 Time (s) JG97.5/3c Outer Detach Fig.. Time evolution of the parameters of an L-mode discharge during a density ramp with strike points on the horizontal target. #3887. (a) Core density ne and neutral beam power P NB. (b) Ratio of the integrated Dγ and Dα intensities at the inner and outer targets. (c) Line integral density at the outer target (d) Integrated ion current to the inner and outer targets. JG98.19/1c 16

rate of rise of density when the plasma detaches from the outer target and the fuelling efficiency increases, Fig. a. This behaviour seems to be characteristic of tokamaks with closed divertors [7]. The Dγ/Dα ratio, Fig. b, measured with the visible spectrometer (KS3) viewing the inner and outer targets separately, at first decreases as the density rises, as is expected from the atomic physics rate coefficients characteristic of excitation only [8,9], and reaches approximately the same value, Dγ/Dα.13, in each case just before detachment. This corresponds to an average divertor density of ~1x1 m -3 [9]. The line integral density measured with the interferometer at the outer target is shown in Fig. c. At the time of outer target detachment it is >5x1 18 m -, corresponding to a maximum density of ~8x1 19 m -3. The interferometer stops working at a line integral density of ~5x1 18 m - due to refraction of the microwaves. Coincident with the change in slope of the ion current there is a large rise in the absolute level of the Dγ and Dα line intensity and an increase in the Dγ/Dα ratio as shown in Fig. b. The abrupt increase in the Dγ/Dα ratio is characteristic of the onset of recombination [,1]. Discharges in hydrogen required higher power to reach the L-H mode transition which allowed L-mode discharges to be studied at input powers of and 6 MW. However, the value of the Dγ/ Dα ratio reached just prior to detachment was the same for these discharges, indicating that plasma conditions were very similar. The electron temperature measured at the probes in the outer target falls to <5eV just before detachment as discussed in detail previously []. The strike points can be moved from the horizontal target (illustrated in Fig. 1) to the vertical target. In this configuration detachment, as measured by the ion saturation cur- a) Pulse No: 3385 n e P rent, and recombination, as measured by the NB Inner Outer Dγ/Dα ratio, both change much more gradually, Fig. 3. The detachment at the inner target γ /D α Inner target Detach Detach.5 b) D. takes place at higher density and the detachment of inner and outer target occur almost si-.15.1 c) Divertor n e dl multaneously. There is a further abrupt reduction in the ion current and change of slope of ne, corresponding to MARFE formation, at d) Ion flux 5 19.8 s. Similar densities, as measured by the 3 Inner target interferometer at the outer target, are required 1 to induce detachment both with the strike point Time (s) on the horizontal and vertical targets and the Fig. 3. Time evolution of the parameters of an L-mode value of the Dγ/Dα ratio at detachment is the discharge during a density ramp with strike points on the vertical target. #3885 (a) Core same. The interferometer chord still goes density ne and neutral beam power P NB. (b) Ratio of the integrated through the SOL in the divertor with the strike Dγ and Dα intensities at the inner and outer targets. (c) point on the vertical target, although the width Line integral density at the outer target (d) Integrated of the SOL along the line of sight is smaller. ion current to the inner and outer targets. Density (1 19 m 3 ) NB Power (MW) Density (1 18 m ) Flux (1 /s) 1 13 1 15 16 17 18 19 JG98.19/c 17

Pulse No. 316 JG98.19/3c The position of the recombination.3 a) Inner Inner target Outer is observed from the Dγ/Dα ratio Detach Detach.5 measured with the cameras, as. shown in Fig.. Because of the finite bandwidth of the filter (1 nm), b) D log1 Ph/m /s α.7.15.8 1.8 care must be taken that the Dγ signal is not contaminated with impu-.69 OSP 1.61 1.38.6 1.15.9.6. ISP.3 rity lines or the CD band at 31 nm, c) D γ /D α both of which tend to occur at low.8 OSP densities. However, by cross-checking with spectrometer data, despite. ISP.6 their poorer spatial resolution, the 1 13 1 15 16 17 18 Time (s) conditions under which the Dγ/Dα Fig.. Time and space development of the Dα intensity and the Dγ/ ratio increases can be ascertained. Dα intensity ratio in an L-mode discharge with MW neutral beam The contour plots of Fig. show that heating and a density ramp induced by gas puffing. The inner (ISP) the Dα intensity is highest at the and outer (OSP) strike points are indicated. Shot #316, Ip =. inner target and is centred near the MA, Bt =.5 T. (a) Ratio of the integrated Dγ and Dα intensities at the inner and outer targets. (b) Contours of Dα intensity (c) Contours of Dγ/Dα intensity ratio inner strike point. The intensity increases as the density rises up to 18.8 s. During this time the maximum in the ratio of Dγ/Dα but moves gradually to larger major radius, ie closer to the x-point, Fig.. The tangential camera view shows that the region of most intense radiation is moving vertically up towards the x-point. Between 17.5 and 18.5 s the Dγ/ Dα ratio at the strike point decreases. This seems unlikely to be due to less recombination. A more probable explanation is that the temperature at the inner target is dropping further. This results in a reduced value of the Dγ/Dα ratio [8,11]. When detachment occurs at the outer target, as indicated by the drop in the ion current at 17.6 s, the increase in the Dγ/Dα ratio and the discontinuity in the density, Fig., the peak Dγ/Dα ratio jumps to a position between R =.6 and.68 m, fig. The rise in the Dγ/Dα ratio at the outer target as seen in Fig., actually corresponds to radiation from near the x-point. No accurate measure of the vertical height of this radiation is available at present but the radial position is similar to that of the total radiation, obtained from a tomographic reconstruction of the bolometer array data. 3.. H-mode discharges R (m) R (m) D γ /D α Contour levels, Contour levels.8.6....18.16.1.1 When higher power neutral beam heating is turned on ( 3 MW in deuterium) there is a rapid transition from L-mode to H-mode with the onset of ELMs and the formation of a temperature pedestal just inside the separatrix [1]. If there is no additional gas puffing the inner target plasma remains detached and the outer target plasma is attached. In H-mode with modest gas puffing ( 1 D/s) recombination is observed at the inner target. 18

Gas puffing has been increased in steps Pulse No: 16 in successive discharges but has little effect on 8 (a) n e Outer 6 Outer reattach the density. The fuelling efficiency decreases detach Γ and the density remains approximately constant 15 (b) 1 P TOT [13,1]. A discharge with high gas puffing 5 (3x1 D/s) is shown in Fig. 5. The increase. PRAD (c) D γ /D α Inner in gas puffing causes the radiated power to increase. target and the energy confinement time to de- 6 (d) Ion current J s probe 3 crease. The H89 factor falls from ~1.8 to 1.5, Fig. 5, as Te, measured by the ECE heterodyne 1.8 (e) H 89 1. radiometer at the pedestal (r/a =.9), drops 1. 1 16 18 from 1. to. kev. At 18 s, after the gas puff Time (s) has been on for about 1 s, the Dγ/Dα ratio, as observed with the spectrometer looking at the 1 5 (f) D α two spatial integrals of the inner and outer targets, shows an upward jump at the outer target Outer detach (g) J s (probe ) and and there is a corresponding drop in the 3 integral ion current to the outer target. Other (h) T e (probe ) 1 features of this transition are a sudden increase 17. 17. 17.8 18. in the power radiated to 5%-6% of the nominal Time (s) input power and an increase in the ELM frequency. The electron temperature Te, measured by the probes in the target near the strike Fig. 5. Time evolution of the parameters of an ELMy H- mode discharge during strong gas puffing #16. (a) Core density ne and deuterium gas puff rate Γ. (b) Total input power, Ptot, and total radiated power, Prad. (c) point, falls to <3 ev, Fig. 5h. There is further Ratio of the integrated Dγ and Dα intensities at the drop in H89. In some cases it falls back to the inner and outer targets (d) Saturated ion current density L-mode level as measured in the same discharge in a phase with lower neutral beam heating. These features are all characteristic of at probe 3 near the strike point on the outer target (e) Scaled energy confinement time H89. (f) Dα intensity at the outer divertor on expanded time scale showing transition from slow to fast ELMs. (g) Ion current to plasma detachment from the outer target. At triple probe, on expanded scale, showing drop in this stage since the ELMs are small, with a frequency current when outer target detaches at 17.93 s (h) Te ~1 Hz, and the H89 factor is less than 1.5 it is a rather poor quality H-mode. When from triple probe, showing drop in temperature when outer target detaches at 17.93 s the gas puff is turned off at 1.8 s the plasma re-attaches at the outer target and the H89 factor begins to rise again. Similar discharges with slightly less gas puffing (<3x1 el/s) can result in a reduction in the pedestal Te, and a deterioration in confinement without leading to detachment provided Te at the target, between ELMs, does not fall below ~5 ev. The ion current to the outer target does not drop. The size of gas puff required to induce detachment does not seem to be strongly dependent on the input power in the 8-1 MW range. Density (1 19 m 3 ) Gas puff (1 s 1 ) 1 5 A/m Power (MW) 1 5 Amps/m Intensity (V) T e (ev) 19 JG98.19/7c

During the detached phase there are large spikes in the ion current to the target and in the plasma temperature, measured by the target probes, which are coincident with the ELM spikes observed on the Dα signal, Figs. 5f,g,h. A triple probe with a time response of.1 ms was used. From the triple probe data the plasma is observed to reattach briefly during the ELMs; the Dγ and Dα spectroscopic signals are too slow to resolve the effects of the ELMs. Less data is available for H-mode discharges with the strike point on the vertical target, but unlike the L- mode there are no obvious differences in the threshold density for detachment between horizontal and vertical targets. The spatial distribution of recombination is much more difficult to determine in H-mode than in L-mode. Recombination can be observed at the inner target during the L-mode phase which preceeds the H-mode condition. When the H-mode develops, the maxima in the Dα, Dγ and CII radiation come from near the strike points. The Dα, and Dγ intensities are about 3 times higher at the inner strike point than the outer but the signals are unfortunately partly saturated during the high gas puffing phase from 17. to.7 s. Data from the camera with the Dγ filter is difficult to interpret in the presence of the ELMs. The spatial distribution of the higher n Balmer series have been measured with the KT3A and KT3B visible spectrometers over the range R =.7 to.9 m during the detached phase of the high power discharges. The spatial distribution of the intensity of these states is compared to the intensity of the Dα and to a tomographic reconstruction of the total radiation from bolometers in Fig. 6. It is seen that, after detachment, while most of the total radiation comes from the outer target near the strike point, the maximum in the Dα radiation still comes from the inner target. This is different from discharges with impurity puffing which result in MARFE formation and radiation from near the x-point [15]. Radiation from the transitions n = 5, n = 6, n = 9, n = 1, and n = 11 are observed at the outer target. The fact that these lines are observable indicates that some recombination is taking place. The high n lines also allow the density along a line of sight to be calculated from the Stark broadening [16]. Densities in the range ne = 3-5x1 m -3 are obtained with very similar results from the analysis of n = 9, n = 1, and n = 11 transitions [5]. The photon emissivity distribution of the various transitions from principal quantum number n = 3 to n = 11 at major radii, R=.8 m and R=.8 m during the detached phase of an H-mode discharge with high gas puffing is shown in Fig. 7. These data have been compared with calculations of the photon emissivity coefficients (PECs) using ADAS atomic data and a radiative-collisional model [11]. The experimental PECs have been obtained from the data by dividing the line intensity by the local ne, measured by the Stark broadening of the high n transitions. There is good agreement between the measured PECs and those calculated for recombination. The absolute values agree with the assumption of a local Te =.7 to 1. ev and an assumed line integral length of the emitting region of.3 m. 11

1 1 photons cm sr 1 s 1 1 3 5 Z (m) 6..3..5.6.7.8.9 3. R (m) MW m 3 1. (c) 1 1. 1.6 1.8 (a) High n Balmer series (b) D α 6 9 1..6.8 3. R (m) Fig. 6. Spatial distribution of total radiation and deuterium radiation in a neutral beam heated discharge, detached at the outer target, #16. Ip=.6 MA, Bt=.7 T, Ptot = 1.6 MW, ne = 7.3x1 19 m -3. Gas puff 3.1x 1 D/s. (a) Intensity of the Balmer series transitions n = 6->, n = 9-> and n = 1->, at the outer target, measured with the visible spectrometers, KT3A/ B (line integrated). (b) Dα intensity from the flux camera, KL (line integrated). (c) Tomographic reconstruction of the total radiation from bolometer array. JG98.35/c 1 8 6 Photon emissivity coefficient (Ph m 3 s 1 ) 1 1 1 13 1 1 Pulse No: 6 ASDAS PEC, T e =.7eV ASDAS PEC, T e = 1.eV Expt, R =.8m Expt, R =.8m 1 15 6 8 1 1 Principal quantum number n Fig. 7. Population distribution of the principal quantum states of deuterium at two major radii, R =.8 m and R =.8 m in a neutral beam heated discharge detached at the outer target by gas puffing. #6. Ip =.6 MA, Bt =.7 T, Ptot = 9. MW, ne = 7.5x1 19 m -3. Gas puff = 3.7x 1 D/s. The experimental data has been compared to the photon emissivity calculated from ADAS [11], dividing by the density measured by Stark broadening (x1 m -3 ) and an assumed radiating depth of.3 m. JG98.35/c. DISCUSSION Detachment and recombination occur when the plasma temperature at the target falls below ~5 ev, as measured by the probes. The radiation moves upwards and increases, causing Te to drop further and recombination to be enhanced. In the case of ohmic and L-mode discharges, further fuelling causes increased density which results in an instability. More power is then radiated than is being applied and the plasma disrupts. In the steady state ELMy H-mode this seldom happens. Increased fuelling has little effect on the density; the fuelling efficiency simply decreases. Thus the detached mode appears to be stable with 5%-6% of the total input power being radiated. It is important to know whether detachment is playing a role in the reduction of confinement. In the H-mode case the effect of gas puffing is to increase the total radiation and to reduce the local edge temperature in the pedestal. The lowered pedestal Te reduces the confinement well before there is any indication of detachment or recombination at the outer target, Fig. 5a. 111

With continued gas puffing the density at the target continues to rise and Te falls until the conditions for detachment and recombination occur, Fig. 5b. They then occur simultaneously within the time resolution of the spectroscopic diagnostics, ~5 ms. At this point the frequency of the ELMs increases. When the gas puffing stops the confinement starts to recover; it does not fully return to the initial H-mode value, possibly becasue it takes time for the gas to pump away. The spatial distribution of the recombination is much more difficult to determine in H-mode than in L-mode. The discharge in Fig. 5 is in L-mode before 16 s and the recombination signal is seen at the inner strike point as in other L-mode discharges. When the transition to H-mode occurs the Dα and Dγ radiation still are predominantly at the inner target. When the outer target detaches, high n states indicating recombination are observed at the outer target with the KT3A/ KT3B spectrometers. The comparison between the approach to detachment in L-mode, with horizontal and vertical targets, is interesting. In the JET Mk I divertor there was little difference between the density required for detachment at the inner and outer targets. In Mk II however, detachment occured at ~3% lower density than in Mk I [6] and, as seen from Figs. and 3, there is a marked difference between detachment on the horizontal and vertical targets. Using the horizontal target, detachment occurs at much lower ne on the inner target than on the outer, while using the vertical target detachment occurs at the inner and outer targets at roughly the same density. The approach to detachment is also rather gradual on the vertical target while on the horizontal one it is quite abrupt. The geometry of the SOL is well known to be different in the two cases, with the recycling neutrals entering the SOL near the hot, dense plasma at the separatrix with the vertical target and going into the low density outer SOL with the horizontal target. This results in quite a different recycling pattern in the two cases. The more symmetric behaviour with vertical targets is possibly caused by the private flux zone being common to the inner and outer separatrices. If it is assumed that the SOL is reasonably transparent to recycling neutrals then the density will build up in the private flux zone (PFZ) between the strike points and the neutral source will be the same for inner and outer separatrices. With the horizontal target the recycling neutrals are separated by the divertor legs and the PFZ. It is thus probable that the difference in the recycling pattern leads to the difference in the detachment behaviour. 5. CONCLUSIONS The onset of recombination coincides with detachment in JET, at both inner and outer divertor targets. The recombination is concentrated around the strike point in both cases. This means that the plasma temperature must locally be <1 ev. After detachment occurs the radiation moves upwards and there is some evidence for recombination occurring at the x-point in L-mode discharges. There is no evidence that this occurs in H-mode conditions. The observation of recombination is a valuable diagnostic which confirms the results from the probes that detachment is more gradual and more symmetric when the strike points are on 11

the vertical targets. When the strike point is on the horizontal targets detachment occurs at lower density on the inner target than at the outer target. Detachment observed with the probes, the Dγ/Dα ratio and the movement of the radiation distribution, all occur during H-mode discharges when a sufficiently high gas injection is applied. However the initial effect of the gas is to reduce Te inside the separatrix at the profile pedestal. This has the consequence of reducing the energy confinement, H89 falling from ~. to <1.5, i.e. no longer being in good H-mode, despite the high power input. With continued gas puffing the outer target detaches. It thus appears that in JET it is not possible to have detached discharges with good H-mode confinement. This is an important conclusion in that the power to the target cannot be spatially dissipated by radiation in the way it can be in ohmic or L-mode plasmas. REFERENCES. [1] D. Lumma, J. L. Terry, and B. Lipschultz, Phys. Plasmas (1997) 555. [] S. I. Krasheninnikov, Phys. Plasmas, (1997) 1638. [3] A. Loarte, J. Nucl. Mater. 1-3 (1997) 118. [] G. M. McCracken, M.F. Stamp, R.D. Monk et al., Nucl. Fusion 38 (1998) in press. [5] A. G. Meigs to be published in Controlled Fusion and Plasma Physics (Proc 5th Eur Conf, Prague 1998). [6] R. D. Monk et al., in Controlled Fusion and Plasma Physics (Proc th Eur Conf, Berchtesgaden 1997), Vol 1A, Pt I, European Physical Society Geneva (1997) 117. [7] G. M. McCracken, B. Lipschultz, B. Labombard et al. Physics of Plasmas (1997) 1681 [8] L. C. Johnson, and E. Hinnov, J. Quant. Spectr. Rad. Transf. 13 (1973) 33. [9] T. Fujimoto, S. Miyachi, and K. Sawada, Nucl. Fusion 8 (1988) 155. [1] J. L. Terry, B. Lipschultz, D. Lumma et al, in Controlled Fusion and Plasma Physics (Proc th Eur Conf, Berchtesgaden 1997), Vol 1A, Pt II, European Physical Society Geneva (1997) 573. [11] H. P. Summers, Atomic Data and Analysis Structure Users Manual, JET Report IR(9) 6, JET Joint Undertaking, Abingdon UK, 199. [1] M. Keilhacker for the JET team. Plasma Phys. and Contr. Fusion 39, Supplement 1B (1997) B1. [13] G. Saibene, B. Balet, S. Clement et al., in Controlled Fusion and Plasma Physics (Proc th Eur Conf, Berchtesgaden 1997), Vol 1A, Pt I, European Physical Society Geneva (1997) 9. [1] G. F. Matthews, P. Andrew, B. Balet et al., this conference. [15] G. F. Matthews, B. Balet, J. G. Cordey et al., submitted to Nuclear Fusion, Mar 1998. Studies in JET divertors of varied geometry, II: impurity seeded plasmas [16] B. L. Welch, H. R. Griem, J. L. Terry et al., Phys. Plasmas (1995) 6. 113