Upgrade of Imaging Bolometers on LHD
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概要
- 論文の詳細を見る
Infrared Imaging Video Bolometers (IRVB) provide an image of the plasma radiation by using a thin metal foil to absorb the radiation, which is then imaged by an IR camera. In LHD IRVBs at Ports 6-T and 1-O have been upgraded. Both of the ∼ 1 micron × 70 mm × 90 mm gold foils have been replaced with ∼ 2.5 micron Pt foils of the same area for greater sensitivity (Pt vs Au) and absorption of higher energy photons estimated up to 8.2 keV. Also the IR cameras have been replaced; an FLIR/SC500 (∼ 100 mK, 60 fps, 320 × 240 pixels) IR camera at Port 1-O with a FLIR/Phoenix (∼ 16 mK, 345 fps, 320 × 256 pixels) IR camera at Port 10-O and an AGEMA/THV 900 LW (∼ 190 mK, 15 fps, 136 × 272 pixels)] with a FLIR SC-4000 (∼ 19 mK, 327 fps, 320 × 256 pixels) IR camera at port 6-T. In the current campaign these IRVBs will use 8 mm × 8 mm apertures resulting in 12 × 16 channels on the foil. The noise equivalent power density for these two new IRVBs ranges from ∼ 360 µW/cm2 for 327 fps operation to 3.6 µW/cm2 for 15 fps operation, which is over two orders of magnitude of improvement over the previous IRVB at Port 6-T.
著者
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ASHIKAWA Naoko
National Institute for Fusion Science
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PETERSON Byron
National Insitute for Fusion Science
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PETERSON Byron
National Institute for Fusion Science, 322-6 Oroshi-cho, Toki-shi, Gifu-ken 509-5292, Japan
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DRAPIKO Evgeny
National Institute for Fusion Science, 322-6 Oroshi-cho, Toki 509-5292, Japan
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SEO Dongcheol
National Fusion Research Center, Daejeon 305-806, Korea
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DRAPIKO Evgeny
National Institute for Fusion Science, 322-6 Oroshi-cho, Toki-shi, Gifu-ken 509-5292, Japan
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DRAPIKO Evgeny
National Institute for Fusion Science
関連論文
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- Increase of Central Ion Temperature after Carbon Pellet Injection in Ne-Seeded NBI Discharges of LHD
- Achievement of 10 keV Central Electron Temperatures by ECH in LHD
- Sustained Detachment with the Self-Regulated Plasma Edge beneath the Last Closed Flux Surface in LHD
- Retention and Desorption of Hydrogen and Helium in Inner Wall Material Used for The Large Helical Device (LHD) : Simulation experiments using a glow discharge apparatus
- Local Impurity Deposition in a Magnetic Island by Means of a Tracer-Encapsulated Solid Pellet in the LHD
- Extension of Improved Particle and Energy Confinement Regime in the Core of LHD Plasma
- Observation of a Rotating Radiation Belt in LHD
- Impurity Deposition and Retention of Discharge Gas on Plasma Facing Wall in LHD
- Impurity Retention Effect in the Edge Ergodic Layer of the Large Helical Device
- Helium Retention of 316L Stainless Steel Used for The First Wall of The Large Helical Device (LHD)
- Increase of Lifetime of Thallium Zeolite Ion Source for Single-Ended Accelerator
- 25pB10p Bolometric Measurements of NBI Heated Plasmas in LHD using Resistive Metal Film Bolometers(ヘリカル/プラズマ応用)
- Comparison of Au and Pt Foils for an Imaging Bolometer
- Axial Profile of Balmer-Alpha Emission near a Tungsten Target in the Compact PWI Simulator APSEDAS
- Progress in Impurity-Related Physics Experiments in LHD
- Upgrade of Imaging Bolometers on LHD
- 29pB13P Impurity Transport Induced Oscillations in LHD
- Fast XUV 16 × 16 Array Hybrid Module for Plasma Imaging Applications
- Thermal Characteristics of Foils for an Imaging Bolometer
- Characterization of Ion Cyclotron Wall Conditioning Using Material Probes in LHD
- Spatial Variation of the Foil Parameters from in Situ Calibration of the JT-60U Imaging Bolometer Foil
- Research and Development of Imaging Bolometers
- Study on the Leakage Fields Prediction of a Static Ferromagnetic Shield in Consideration of Hysteresis and Residual Strain of Shielding Materials
- Hydrogen Retention Behavior in Boron Films Affected by Impurities Introduced by Hydrogen Plasma Exposure in the LHD
- Toroidal Distributions of Amounts of Retained Gases and Deposited Impurities during 13th Experimental Campaign in the LHD
- Density Regimes of Complete Detachment and Serpens Mode in LHD
- Infrared Imaging Video Bolometer with a Double Layer Absorbing Foil
- Multi-Functional Diagnostic Method with Tracer-Encapsulated Pellet Injection
- Characterization of Dust Particles Ranging in Size from 1 nm to 10 µm Collected in the LHD
- Investigation of Carbon Films on Material Probes in the Vicinity of Local Island Divertor in the Large Helical Device
- Characteristics of Radiating Collapse at the Density Limit in the Large Helical Device
- Determination of the Major Impurity Radiators in the Reheat Mode Discharges in the Compact Helical System
- Flux Control of Carbon Nanoparticles Generated due to Interactions between Hydrogen Plasmas and Graphite Using DC-Biased Substrates
- A Simple Method of H/He Influx Ratio Measurement as a Monitor for Machine Operation in LHD
- Tritium Retention on Stainless Steel Surface Exposed to Plasmas in LHD
- Foil Calibration for IR Imaging Bolometer by Laser Irradiation
- Flux Control of Carbon Nanoparticles Generated due to Interactions between Hydrogen Plasmas and Graphite Using DC-Biased Substrates (Special Issue : Advanced Plasma Science and Its Applications for Nitrides and Nanomaterials)
- Behaviors of Deuterium Retention and Microstructure Change of Tungsten Simultaneously Implanted with Carbon and/or Helium Ions