GA A26741 SCINTILLATOR-BASED DIAGNOSTIC FOR FAST ION LOSS MEASUREMENTS ON DIII-D

Similar documents
GA A25853 FAST ION REDISTRIBUTION AND IMPLICATIONS FOR THE HYBRID REGIME

GA A26686 FAST ION EFFECTS DURING TEST BLANKET MODULE SIMULATION EXPERIMENTS IN DIII-D

GA A26474 SYNERGY IN TWO-FREQUENCY FAST WAVE CYCLOTRON HARMONIC ABSORPTION IN DIII-D

Neutral Beam-Ion Prompt Loss Induced by Alfvén Eigenmodes in DIII-D

GA A22722 CENTRAL THOMSON SCATTERING UPGRADE ON DIII D

GA A27806 TURBULENCE BEHAVIOR AND TRANSPORT RESPONSE APPROACHING BURNING PLASMA RELEVANT PARAMETERS

Beam Driven Alfvén Eigenmodes and Fast Ion Transport in the DIII-D and ASDEX Upgrade (AUG) Tokamaks

GA A23713 RECENT ECCD EXPERIMENTAL STUDIES ON DIII D

UPGRADED CALIBRATIONS OF THE THOMSON SYSTEM AT DIII D

GA A23736 EFFECTS OF CROSS-SECTION SHAPE ON L MODE AND H MODE ENERGY TRANSPORT

STABILIZATION OF m=2/n=1 TEARING MODES BY ELECTRON CYCLOTRON CURRENT DRIVE IN THE DIII D TOKAMAK

Scaling of divertor heat flux profile widths in DIII-D

SciDAC CENTER FOR SIMULATION OF WAVE-PLASMA INTERACTIONS

Plasma Response Control Using Advanced Feedback Techniques

GA A27235 EULERIAN SIMULATIONS OF NEOCLASSICAL FLOWS AND TRANSPORT IN THE TOKAMAK PLASMA EDGE AND OUTER CORE

GA A22571 REDUCTION OF TOROIDAL ROTATION BY FAST WAVE POWER IN DIII D

GA A27857 IMPACT OF PLASMA RESPONSE ON RMP ELM SUPPRESSION IN DIII-D

Excitation of Alfvén eigenmodes with sub-alfvénic neutral beam ions in JET and DIII-D plasmas

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

PLASMA MASS DENSITY, SPECIES MIX AND FLUCTUATION DIAGNOSTICS USING FAST ALFVEN WAVE

UNDERSTANDING TRANSPORT THROUGH DIMENSIONLESS PARAMETER SCALING EXPERIMENTS

GA A24016 PHYSICS OF OFF-AXIS ELECTRON CYCLOTRON CURRENT DRIVE

TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D

GA A27805 EXPANDING THE PHYSICS BASIS OF THE BASELINE Q=10 SCENRAIO TOWARD ITER CONDITIONS

RWM FEEDBACK STABILIZATION IN DIII D: EXPERIMENT-THEORY COMPARISONS AND IMPLICATIONS FOR ITER

GA A22689 SLOW LINER FUSION

GA A THERMAL ION ORBIT LOSS AND RADIAL ELECTRIC FIELD IN DIII-D by J.S. degrassie, J.A. BOEDO, B.A. GRIERSON, and R.J.

GA A26785 GIANT SAWTEETH IN DIII-D AND THE QUASI-INTERCHANGE MODE

GA A27290 CALCULATION OF IMPURITY POLOIDAL ROTATION FROM MEASURED POLOIDAL ASYMMETRIES IN THE TOROIDAL ROTATION OF A TOKAMAK PLASMA

IMPACT OF EDGE CURRENT DENSITY AND PRESSURE GRADIENT ON THE STABILITY OF DIII-D HIGH PERFORMANCE DISCHARGES

GA A23797 UTILIZATION OF LIBEAM POLARIMETRY FOR EDGE CURRENT DETERMINATION ON DIII-D

Overview of equilibrium reconstruction on DIII-D using new measurements from an expanded motional Stark effect diagnostic

GA A25351 PHYSICS ADVANCES IN THE ITER HYBRID SCENARIO IN DIII-D

GA A23977 DETAILED MEASUREMENTS OF ECCD EFFICIENCY ON DIII D FOR COMPARISON WITH THEORY

Princeton University, Plasma Physics Laboratory, PO Box 451, Princeton, New Jersey , USA. Abstract

in the pinch. This paper describes the computer modeling behind the shielding design of a

CONTRIBUTIONS FROM THE NEUTRAL BEAMLINE IRON TO PLASMA NON-AXISYMMETRIC FIELDS

GA A25658 PRECISION X-RAY OPTICAL DEPTH MEASUREMENTS IN ICF SHELLS

PREDICTIVE MODELING OF PLASMA HALO EVOLUTION IN POST-THERMAL QUENCH DISRUPTING PLASMAS

Fast Ion Effects during Test Blanket Module Simulation Experiments in DIII-D

Diagnostics for Burning Plasma Physics Studies: A Status Report.

GA A23698 ELECTRON CYCLOTRON WAVE EXPERIMENTS ON DIII D

GA A26057 DEMONSTRATION OF ITER OPERATIONAL SCENARIOS ON DIII-D

GA A23114 DEPENDENCE OF HEAT AND PARTICLE TRANSPORT ON THE RATIO OF THE ION AND ELECTRON TEMPERATURES

GA A23198 HORIZONTAL THOMSON SCATTERING SYSTEMS FOR DIII D AND SSPX

Multicusp Sources for Ion Beam Lithography Applications

Thin Faraday foil collectors as a lost ion diagnostic

GA A26732 DEUTERIUM VELOCITY AND TEMPERATURE MEASUREMENTS ON THE DIII-D TOKAMAK

GA A24166 SUPER-INTENSE QUASI-NEUTRAL PROTON BEAMS INTERACTING WITH PLASMA: A NUMERICAL INVESTIGATION

GA A25410 DISRUPTION CHARACTERIZATION AND DATABASE ACTIVITIES FOR ITER

Impurity Transport Studies of Intrinsic MO and Injected Ge in High Temperature ECRH Heated FTU Tokamak Plasmas

GA A26807 RESULTS OF ITER TEST BLANKET MODULE MOCK-UP EXPERIMENTS ON DIII-D

Simulation of Double-Null Divertor Plasmas with the UEDGE Code

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

Transport Improvement Near Low Order Rational q Surfaces in DIII D

GA A23403 GAS PUFF FUELED H MODE DISCHARGES WITH GOOD ENERGY CONFINEMENT ABOVE THE GREENWALD DENSITY LIMIT ON DIII D

Applications of Pulse Shape Analysis to HPGe Gamma-Ray Detectors

MHD Induced Fast-Ion Losses in ASDEX Upgrade

GA A26110 MEASUREMENTS OF THE INTERNAL MAGNETIC FIELD ON DIII-D USING INTENSITY AND SPACING OF THE MOTIONAL STARK MULTIPLET

EVIDENCE FOR ANOMALOUS EFFECTS ON THE CURRENT EVOLUTION IN TOKAMAK OPERATING SCENARIOS

A Distributed Radiator, Heavy Ion Driven Inertial Confinement Fusion Target with Realistic, Multibeam Illumination Geometry

Fission-Fusion Neutron Source

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

BWXT Y-12 Y-12. A BWXT/Bechtel Enterprise SMALL, PORTABLE, LIGHTWEIGHT DT NEUTRON GENERATOR FOR USE WITH NMIS

GA A27444 PROBING RESISTIVE WALL MODE STABILITY USING OFF-AXIS NBI

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

Role of Flow Shear in Enhanced Core Confinement

Shock compression of precompressed deuterium

Fast particle-driven ion cyclotron emission (ICE) in tokamak plasmas and the case for an ICE diagnostic in ITER

GA A23168 TOKAMAK REACTOR DESIGNS AS A FUNCTION OF ASPECT RATIO

GA A27933 TURBULENCE BEHAVIOR AND TRANSPORT RESPONSE APPROACHING BURNING PLASMA RELEVANT PARAMETERS

12/16/95-3/15/96 PERIOD MULTI-PARAMETER ON-LINE COAL BULK ANALYSIS. 2, 1. Thermal Neutron Flux in Coal: New Coal Container Geometry

Nonlinear Evolution and Radial Propagation of the Energetic Particle Driven GAM

GA A26866 REDUCED ELECTRON THERMAL TRANSPORT IN LOW COLLISIONALITY H-MODE PLASMAS IN DIII-D AND THE IMPORTANCE OF SMALL-SCALE TURBULENCE

CQNl_" RESPONSE TO 100% INTERNAL QUANTUM EFFICIENCY SILICON PHOTODIODES TO LOW ENERGY ELECTRONS AND IONS

MHD-Induced Alpha Particle Loss in TFTR. S.J. Zweben, D.S. Darrow, E.D. Fredrickson, G. Taylor, S. von Goeler, R.B. White

GA A27437 SCALING OF THE DIVERTOR HEAT FLUX WIDTH IN THE DIII-D TOKAMAK

Alpha-particle physics in the tokamak fusion test reactor DT experiment

Generation of Plasma Rotation in a Tokamak by Ion-Cyclotron Absorption of Fast Alfven Waves

DIAGNOSTICS FOR ADVANCED TOKAMAK RESEARCH

A NEW TARGET CONCEPT FOR PROTON ACCELERATOR DRIVEN BORON NEUTRON CAPTURE THERAPY APPLICATIONS* Brookhaven National Laboratory. P.O.

GA A25592 STABILITY AND DYNAMICS OF THE EDGE PEDESTAL IN THE LOW COLLISIONALITY REGIME: PHYSICS MECHANISMS FOR STEADY-STATE ELM-FREE OPERATION

GA A26242 COMPREHENSIVE CONTROL OF RESISTIVE WALL MODES IN DIII-D ADVANCED TOKAMAK PLASMAS

GA A22993 EFFECTS OF PLASMA SHAPE AND PROFILES ON EDGE STABILITY IN DIII D

Analysis of D Pellet Injection Experiments in the W7-AS Stellarator*

Optimization of NSLS-II Blade X-ray Beam Position Monitors: from Photoemission type to Diamond Detector. P. Ilinski

Impact of Localized ECRH on NBI and ICRH Driven Alfven Eigenmodes in the ASDEX Upgrade Tokamak

FUSION WITH Z-PINCHES. Don Cook. Sandia National Laboratories Albuquerque, New Mexico 87185

GA A27433 THE EPED PEDESTAL MODEL: EXTENSIONS, APPLICATION TO ELM-SUPPRESSED REGIMES, AND ITER PREDICTIONS

GA A22877 A NEW DC MAGNETIC SENSOR

GA A26116 THE CONCEPTUAL MODEL OF THE MAGNETIC TOPOLOGY AND NONLINEAR DYNAMICS OF

Parametric Instabilities in Laser/Matter Interaction: From Noise Levels to Relativistic Regimes

Development of a High Intensity EBIT for Basic and Applied Science

FUSION TECHNOLOGY INSTITUTE

TAE internal structure through high-resolution soft x-ray measurements in ASDEX-Upgrade. Abstract

Two-Screen Method for Determining Electron Beam Energy and Deflection from Laser Wakefield Acceleration

Energetic Particle Physics in Tokamak Burning Plasmas

Study of chirping Toroidicity-induced Alfvén Eigenmodes in the National Spherical Torus Experiment

GA A26887 ADVANCES TOWARD QH-MODE VIABILITY FOR ELM-FREE OPERATION IN ITER

Fast-ion D measurements and simulations in quiet plasmas

Transcription:

GA A26741 SCINTILLATOR-BASED DIAGNOSTIC FOR FAST ION LOSS MEASUREMENTS ON DIII-D by R.K. FISHER, D.C. PACE, M. GARCÍA-MUÑOZ, W.W. HEIDBRINK, C.M. MUSCATELLO, M.A. VAN ZEELAND and Y.B. ZHU JUNE 2010

DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

GA A26741 SCINTILLATOR-BASED DIAGNOSTIC FOR FAST ION LOSS MEASUREMENTS ON DIII-D by R.K. FISHER, D.C. PACE,* M. GARCÍA-MUÑOZ, W.W. HEIDBRINK,* C.M. MUSCATELLO,* M.A. VAN ZEELAND and Y.B. ZHU* This is a preprint of a paper to be presented at the 18th Topical Conference on High Temperature Plasma Diagnostics, May 16 20, 2010 in Wildwood, New Jersey and to be published in Review of Scientific Instruments. *University of California-Irvine, Irvine, California USA Max Planck-Institut für Plasmaphysik, Garching, Germany Work supported in part by the U.S. Department of Energy under DE-FC02-04ER54698, SC-G903402 and DE-FG03-94ER54271 GENERAL ATOMICS ATOMICS PROJECT 30200 JUNE 2010

ABSTRACT A new scintillator-based fast ion loss detector (FILD) has been installed on DIII-D with the time response (>100 khz) needed to study energetic ion losses induced by Alfvén eigenmodes and other MHD instabilities. Based on the design used on ASDEX Upgrade, the diagnostic measures the pitch angle and gyroradius of ion losses based on the position of the ions striking the 2D scintillator. For fast time response measurements, a beam splitter and fiberoptics couple a portion of the scintillator light to a photomultiplier. Reverse orbit following techniques trace the lost ions to their possible origin within the plasma. Initial DIII-D results showing prompt losses and energetic ion loss due to MHD instabilities are discussed. General Atomics Report GA A26741 iii

I. SUMMARY AND INTRODUCTION Fast ions from neutral beam injection, ion cyclotron heating, and fusion reactions play a fundamental role in the heating and stability of tokamak plasmas. Sawteeth and tearing modes affect fast ion confinement, while large fast ion densities can drive collective instabilities, including Alfvén eigenmodes (AEs). The effects of MHD activity on fast ions can significantly impact the plasma performance. Losses of energetic alpha particles from DT fusion in ITER will reduce the alpha heating available to reach ignition, and have the potential to cause major damage to the first wall. Given their importance for burning plasma experiments in ITER, fast ion studies have become a high priority area for experimental research on DIII-D. The internal mode structures of the fast ion induced instabilities inside the DIII-D plasma have been measured using ECE, BES, FIR scattering, reflectometry, and CO 2 interferometry measurements. 1 Measured profiles of the confined beam ions in DIII-D using the recently developed fast ion D α spectroscopy (FIDA) 2 show that instabilities redistribute fast ions radially outward. Faraday collector-based beam ion loss detectors (BILD) have been used to obtain information on fast ion losses near the outer midplane of DIII-D. 3 We recently installed a new fast ion loss detector (FILD) on DIII-D. By correlating the beam ion loss results from the new FILD with the other fast ion diagnostics and with observations of the internal mode structures in DIII-D, we gain important information on the fast ion loss orbits and loss mechanisms involved in the instabilities. Using the measured pitch angle and energy of the fast ion losses, reverse orbit following techniques can be used to trace the lost ions to their possible origin within the plasma. 4 The initial results of the FILD diagnostic showing prompt losses and beam ion losses due to MHD instabilities will be discussed. General Atomics Report GA A26741 1

II. NEW FAST ION LOSS DETECTOR The FILD detector is installed through a radial port located below the outer midplane of DIII-D. As shown in Fig. 1, this detector can be inserted past the first wall tiles and into the region outside the last closed plasma flux surface, which allows the detection of escaping fast ions over a larger portion of phase space than the BILD detectors which are recessed behind the plasma facing tiles at the outer midplane. The FILD detector measures fast ions that pass through a small entrance aperture in its graphite heat shield and strike a scintillator-coated plate. Measuring the two-dimensional light pattern from the scintillator yields information on both the perpendicular gyroradius and the pitch angle of the escaping fast ions, an approach first used to detect escaping fusion products, 5 and more recently used to study losses of energetic ions from RF heating and neutral beam heating. 6 FIG. 1. FILD detector is inserted into the region below the midplane of DIII-D and outside the last closed plasma flux surface. Figure 2 shows a schematic drawing of the FILD diagnostic. The detector head has a graphite heat shield (diameter ~8.9 cm) to protect the detector from the plasma and beam ion heat loads. Thermocouples located just inside the graphite heat shield are used to monitor the temperature of the detector head. The scintillator plate is mounted on the backside of the graphite end cap so that it can be viewed through a vacuum window at the opposite end of the FILD. The ion entrance aperture is ~15 mm from the plane of the scintillator. The aperture is oriented to accept ions traveling in the same direction as the plasma current. The line from the center of the aperture to the center of the scintillator lies ~45 deg above the direction of the total magnetic field. Based on the AUG design and orbit modeling calculations, the entrance aperture is 1.1 mm by 3 mm to provide adequate gyroradius and pitch angle resolution, respectively. The calculated gyroradius resolution of the FILD is ~1.4 cm for the full energy component, while the pitch angle resolution is ~ 6 deg at a gyroradius of 2.5 cm. Choosing a smaller aperture would have improved the resolution, but would have reduced the FILD signal level and made it more difficult to study high frequency instabilities. Light from the scintillator is collected by a 5 cm diameter objective lens with a General Atomics Report GA A26741 3

R.K. Fisher et al. focal length of 60 cm that is located 60 cm from the scintillator. The spatial distribution of the scintillation light is imaged using a PCO Pixelfly VGA CCD camera with a Navitar f/n1.8 zoom lens, which has a focal length range of 10 110 mm. The camera and zoom lenses are mounted to the back of the FILD diagnostic just behind a vacuum window, and move radially with the insertion of the detector head, so that the optical views remain constant. The camera frame rate is adjustable and provides a maximum sampling of ~160 Hz. The Pixelfly camera is located very close to DIII-D but has not required shielding against magnetic fields or against neutron and gamma-ray radiation. We have not observed any signs of radiation damage after several months of operating the Pixelfly camera in the neutron and gamma-ray environment on DIII-D. We did observe the typical neutron or gamma-ray induced noise in the form of individual saturated pixels during the plasma discharge. FIG. 2. Light from the FILD scintillator is imaged onto camera and fiber-coupled PMT using beam splitter, mirror and two zoom lenses mounted just behind vacuum window. 7 The TG-Green scintillator, first used on the AUG fast ion loss detector, 6 has a 490 ns decay time, high light generation (ionoluminescense) efficiency, and high saturation levels. For fast time response measurements, a beam splitter cube couples ~50% of the scintillation light to a second 10 110 mm zoom lens designed to image the entire scintillator onto the input of a single 1500 µm diameter fiber. This single fused silica fiber couples the scintillation light to a Hamamatsu H5783 photomultiplier tube. The PMT output current is amplified by an Advance Research Instruments PMT-4V3 fast amplifier, operating at a gain of 0.1 V/µA. The resulting signal is then digitized at 1 MHz, allowing measurements of the beam ion losses with the time response (>100 khz) and detection sensitivity needed to study Alfvén eigenmodes and other high frequency MHD instabilities. 4 General Atomics Report GA A26741

III. EXPERIMENTAL RESULTS The FILD diagnostic has been installed and operating for approximately five months of DIII-D operation. First orbit losses have been used to test the FILD capabilities and performance. Pulsing the neutral beam sources while slowly ramping up the plasma current allows observation of the first orbit losses from each of the beam lines. Figure 3 shows that large first orbit losses are observed from the two ion sources (210L and 210R) that inject through a port near to the 225 deg toroidal location of the FILD. A camera image of the 2D scintillation light pattern on the scintillator is shown in the lower portion of Fig. 3. The red grid lines show the calculated pitch angle and gyroradius based on the detector geometry, aperture location, and magnetic equilibrium. First orbit losses from 210L neutral beam appear at a pitch angles ~70 deg, in agreement with the reverse orbit calculations for this detector location [4]. For the 210R injection at 440 ms, we observe losses at a pitch angle of ~55 deg, again in agreement with our reverse orbit calculations. The total magnetic field at the detector is ~1.5 T, so that the corresponding gyroradii for the full, one-half, and one-third energy components of the 75 kev deuterium beams are ~ 3.8, 2.7, and 2.2 cm, respectively. The gyroradius resolution of the FILD is on the order of 1.4 cm for the full energy component. The light pattern on the scintillator shown in Fig. 3 appears consistent with the energies and pitch angles expected for first orbit losses from the 210L beam. FIG. 3. First orbit losses were observed during pulsed operation of neutral beam sources while slowly increasing plasma current. 7 The FILD PMT signal measures the time dependence of the fast ion loss signal on a microsecond time scale. Figure 4 shows the PMT signal and one of the signals from the FIDA diagnostic as a function of time near the start of one of the beam pulses from the 210R General Atomics Report GA A26741 5

R.K. Fisher et al. beamline on DIII-D. The FIDA signal is the D α light resulting from confined beam ions interacting with the 210R beam injected neutrals. Hence the onset of the FIDA signal indicates the start of the 210R beam pulse. The onset of the FILD PMT signal is delayed by 40-50 µs, which is consistent with the transit time for the beam ions over the prompt loss orbit, shown on the right side of Fig. 4, calculated by reverse orbit following techniques [4]. The red X marking the end of the orbit indicates the FILD location. FIG. 4. The measured loss signal is delayed by ~40 50 µs, as expected based on the transit time for first orbit losses. 7 Beam ion losses have also been observed as a result of a number of MHD instabilities, including neoclassical tearing modes, q = 2 fishbones, and Alfvén Eigenmode (AE) activity. Figure 5 shows the measured beam ion loss signals during AE activity increased significantly once the FILD entrance aperture was inserted past the front face of the plasma tiles, but then remained nearly constant as the detector head was inserted further into the region outside the last closed plasma flux surface. As shown in Fig. 1, the detector head always remains at least 10 cm outside of the last closed flux surface at this port location below the plasma midplane. FIG. 5. Measured loss signals from the 210R (red circles) and 210L (blue squares) during AE activity were nearly constant once the ion entrance aperture was inserted past the front face of the plasma wall tiles. 7 6 General Atomics Report GA A26741

Because the detector head is located near one of the counter-injected neutral heating beams on DIII-D, we observed a large prompt loss signal due to this beam. The large flux of energetic beam ions resulting from the first orbit losses caused local scintillator damage, as evidenced by a drop in the scintillator emission in subsequent shots. The scintillator region near 70 deg pitch angle and 3.5 to 4 cm gyroradius (lower portion of bright region on the left in Fig. 3) showed the largest damage. Despite this limitation, the fast response and high scintillation efficiency of the TG-Green scintillator allows measurements at the high frequencies of interest for many MHD instabilities, including Alfvén Eigenmodes. The observed losses resulting from neoclassical tearing modes, q = 2 fishbones, and AE activity are still being analyzed and will be discussed in subsequent papers in our efforts to better understand how the instabilities interact with the fast ions. General Atomics Report GA A26741 7

REFERENCES 1 M. A. Van Zeeland, G. J. Kramer, M. E. Austin, R. L. Boivin, W. W. Heidbrink, M. A. Makowski, G. R. McKee, R. Nazikian, W. M. Solomon, and G. Wang, Phys. Rev. Lett. 97, 135001 (2006). 2 W. W. Heidbrink, N. N. Gorelenkov, Y. Luo, M. A. Van Zeeland, R. B., White, M. E. Austin, K. H. Burrell, G. J. Kramer, M. A. Makowski, G. R. McKee, and R. Nazikian, Phys. Rev. Lett. 99, 245002 (2007). 3 Y. B. Zhu, W. W. Heidbrink, and L. D. Pickering, Phenomenology of Energetic Ion Loss from the DIII-D Tokamak, accepted for publication in Nucl. Fusion, May 2010. 4 D. C. Pace, R. K. Fisher, M. Garcia-Munoz, D. S. Darrow, W. W. Heidbrink, C. M. Muscatello, R. Nazikian, M. A. Van Zeeland, and Y. B. Zhu, Modeling the Response of a Fast Ion Loss Detector Using Orbit Tracing Techniques in a Neutral Beam Prompt Loss Study on the DIII-D Tokamak, this conference (2010). 5 S. J. Zweben, et al., Nucl. Fusion 30, 1551 (1990); D. Darrow, et al., Rev. Sci. Instrum. 77, 10E701 (2006). 6 M. Garcia-Muñoz, H.-U. Fahrbach, and H. Zohm, Rev. Sci. Instrum. 80, 053503 (2009); A. Werner, et al., Rev. Sci. Instrum. 72, 780 (2001); K. Shinohara, et al., Rev. Sci. Instrum. 77, 10E521 (2006); D. Darrow, Rev. Sci. Instrum. 79, 023502 (2008). 7 R.K. Fisher, D.C. Pace, M. García-Muñoz, R.L. Boivin, E.D. Frederickson, W.W. Heidbrink, C.M. Muscatello, R. Nazikian, C.C. Petty, M.A. Van Zeeland, and Y.B. Zhu, Measurements of Beam Ion Losses on DIII-D due to MHD Instabilities, Proc. 37th EPS Conf. on Plasma Physics, 2010, Dublin, Ireland. General Atomics Report GA A26741 9

ACKNOWLEDGMENT Work supported in part by the U.S. Department of Energy under DE-FC02-04ER54698, SC-G903402 and DE-FG03-94ER54271. General Atomics Report GA A26741 11