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Nuclear aspects of tokamak fusion test reactor (TFTR) diagnostics and instrumentation

Description: There are five principal aspects of the nuclear radiation from the high temperature plasmas of TFTR on its plasma diagnostic equipment. i) Important information about the plasma properties to be obtained from measurement of the neutrons, or other fusion reaction products. ii) Experimental studies to give design data for future tokamak devices and their instrumentation. iii) Transient noise or damage effects on the array of detectors for the collection of physics data about the plasma. iv) The e… more
Date: January 1, 1982
Creator: Young, K.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Diagnostic problems of large tokamaks

Description: The increase in scale of Tokamaks, together with the very large power input from auxiliary heating, lead to a requirement for new diagnostic techniques. The reference plasma parameters used in establishing this requirement for this review paper are those predicted for the operation of TFTR. The physics aspects of the diagnostic methods are described with particular inference on areas of interest to atomic physicists.
Date: August 1, 1977
Creator: Young, K. M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Plasma diagnostics for the compact ignition tokamak

Description: The primary mission of the Compact Ignition Tokamak (CIT) is to study the physics of alpha-particle heating in an ignited D-T plasma. A burn time of about 10 /tau//sub E/ is projected in a divertor configuration with baseline machine design parameters of R=2.10 m, 1=0.65 m, b=1.30 m, I/sub p/=11 MA, B/sub T/=10 T and 10-20 MW of auxiliary rf heating. Plasma temperatures and density are expected to reach T/sub e/(O) /approximately/20 keV, T/sub i/(O) /approximately/30 keV, and n/sub e/(O) /appro… more
Date: June 1, 1988
Creator: Medley, S. S. & Young, K. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Alpha-particle diagnostics

Description: This paper will focus on the state of development of diagnostics which are expected to provide the information needed for {alpha}- physics studies in the future. Conventional measurement of detailed temporal and spatial profiles of background plasma properties in DT will be essential for such aspects as determining heating effectiveness, shaping of the plasma profiles and effects of MHD, but will not be addressed here. This paper will address (1) the measurement of the neutron source, and hence… more
Date: January 1, 1991
Creator: Young, K.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Requirements for ITER diagnostics

Description: The development and design of plasma diagnostics for the International Thermonuclear Experimental Reactor (ITER) present a formidable challenge for experimental plasma physicists. The large plasma size, the high central density and temperature and the very high thermal wall loadings provide new challenges for present measurement techniques and lead to a search for new methods. But the physics and control requirements for the long burn phase of the discharge, combined with very limited access to… more
Date: January 1, 1991
Creator: Young, K.M.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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The status of alpha-particle diagnostics

Description: There is a flurry of activity to complete alpha-particle diagnostics so that they can undergo some experimental testing in DT plasmas on JET or TFTR prior to implementation on ITER. Successful measurements of escaping charged fusion products have been made in DD plasmas, and the {alpha}-particle source can be well characterized by neutron profile measurement. These methods can be extrapolated to DT plasmas. Measurement of the confined {alpha}-particles requires a new technique. Collective Thoms… more
Date: January 1, 1992
Creator: Young, K. M. & Johnson, D. W.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Ion cyclotron and spin-flip emissions from fusion products in tokamaks

Description: Power emission by fusion products of tokamak plasmas in their ion cyclotron range of frequencies (ICRF) and at their spin-flip resonance frequency is calculated for some specific model fusion product velocity-space distribution functions. The background plasma of say deuterium (D) is assumed to be in equilibrium with a Maxwellian distribution both for the electrons and ions. The fusion product velocity distributions analyzed here are: (1) A monoenergetic velocity space ring distribution. (2) A … more
Date: February 1, 1993
Creator: Arunasalam, V.; Greene, G. J. & Young, K. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ion cyclotron and spin-flip emissions from fusion products in tokamaks

Description: Power emission by fusion products of tokamak plasmas in their ion cyclotron range of frequencies (ICRF) and at their spin-flip resonance frequency is calculated for some specific model fusion product velocity-space distribution functions. The background plasma of say deuterium (D) is assumed to be in equilibrium with a Maxwellian distribution both for the electrons and ions. The fusion product velocity distributions analyzed here are: (1) A monoenergetic velocity space ring distribution. (2) A … more
Date: February 1, 1993
Creator: Arunasalam, V.; Greene, G. J. & Young, K. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TPX diagnostics for tokamak operation, plasma control and machine protection

Description: The diagnostics for TPX are at an early design phase, with emphasis on the diagnostic access interface with the major tokamak components. Account has to be taken of the very severe environment for diagnostic components located inside the vacuum vessel. The placement of subcontracts for the design and fabrication of the diagnostic systems is in process.
Date: August 1, 1995
Creator: Edmonds, P. H.; Medley, S. S. & Young, K. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary of TFTR (Tokamak Fusion Test Reactor) diagnostics, including JET (Joint European Torus) and JT-60

Description: The diagnostic instrumentation on TFTR (Tokamak Fusion Test Reactor) and the specific properties of each diagnostic, i.e., number of channels, time resolution, wavelength range, etc., are summarized in tables, grouped according to the plasma parameter measured. For comparison, the equivalent diagnostic capabilities of JET (Joint European Torus) and the Japanese large tokamak, JT-60, as of late 1987 are also listed in the tables. Extensive references are given to publications on each instrument.
Date: May 1, 1990
Creator: Hill, K. W.; Young, K. M. & Johnson, L. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Observations of Flaking of Co-deposited Layers in TFTR

Description: Flaking of co-deposited layers in the Tokamak Fusion Test Reactor (TFTR) has been observed after the termination of plasma operations. This unexpected flaking affects approximately 15% of the tiles and appears on isotropic graphite tiles but not on carbon fiber composite tiles. Samples of tiles, flakes and dust were recently collected from the inside of the vacuum vessel and will be analyzed to better characterize the behavior of tritium on plasma facing components in DT fusion devices.
Date: November 1, 1999
Creator: Gentile, C. A.; Skinner, C. H. & Young, K. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Characterization of the TFTR plasma edge by Langmuir-calorimeter probes

Description: Two combination Langmuir-calorimeter probes were operated on the TFTR midplane to measure plasma properties of the scrape-off layer. Two different caloriemter elements were used: 0.5 x 3 x 8 mm Ta plates or 6.4 mm diameter graphite rods fitted with thermocouples. Separate graphite rods served as Langmuir elements. This paper presents Langmuir probe measurements of the radial profiles of edge density and electron temperature, and calorimeter measurements of heat flux. The variation of these quan… more
Date: March 1, 1986
Creator: Kilpatrick, S. J.; Manos, D. M.; Budny, R. V.; Stangeby, P. C.; Ritter, R. S. & Young, K. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Neutral beam interlock system on TFTR using infrared pyrometry

Description: Although the region of the TFTR vacuum vessel wall which is susceptible to damage by neutral beam strike is armored with a mosaic of TiC-clad POCO graphite titles, at power deposition levels above 2.5 kW/cm/sup 2/ the armor surface temperature exceeds 1200/sup 0/C within 250 ms and itself becomes susceptible to damage. In order to protect the wall armor, a neutral beam interlock system based on infrared pyrometry measurement of the armor surface temperature was installed on TFTR. For each beaml… more
Date: June 1, 1986
Creator: Medley, S. S.; Kugel, H. W.; Kozub, T. A.; Lowrance, J. L.; Mastrocola, V.; Renda, G. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Alpha-physics and measurement requirements for ITER

Description: This paper reviews alpha particle physics issues in ITER and their implications for alpha particle measurements. A comparison is made between alpha heating in ITER and NBI and ICRH heating systems in present tokamaks, and alpha particle issues in ITER are discussed in three physics areas: `single particle` alpha effects, `collective` alpha effects, and RF interactions with alpha particles. 29 refs., 4 figs., 4 tabs.
Date: December 31, 1995
Creator: Zweben, S. J.; Young, K. M.; Putvinski, S.; Petrov, M. P.; Sadler, G. & Tobita, K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Visual Detection System for Determining Tritium Surface Deposition Employing Phosphor Coated Materials

Description: A method for visually observing tritium deposition on the surface of the Tokamak Fusion Test Reactor (TFTR) deuterium-tritium (D-T) tiles is being investigated at the Princeton Plasma Physics Laboratory. A green phosphor (P31, zinc sulfide: copper) similar to that used in oscilloscope screens with a wavelength peak of 530 nm was positioned on the surface of a TFTR D-T tile. The approximately 600 gram tile, which contains approximately 1.5 Ci of tritium located on the top approximately 1-50 micr… more
Date: October 1, 1999
Creator: Gentile, C. A.; Skinner, C. H.; Young, K. M. & Zweben, S. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-situ Tritium Measurements of the Tokamak Fusion Test Reactor Bumper Limiter Tiles Post D-T Operations

Description: The Princeton Plasma Physics Laboratory (PPPL) Engineering and Research Staff in collaboration with members of the Japan Atomic Energy Research Institute (JAERI), Tritium Engineering Laboratory have commenced in-situ tritium measurements of the TFTR bumper limiter. The Tokamak Fusion Test Reactor (TFTR) operated with tritium from 1993 to 1997. During this time {approximately} 53,000 Ci of tritium was injected into the TFTR vacuum vessel. After the cessation of TFTR plasma operations in April 19… more
Date: September 1, 1999
Creator: Gentile, C. A.; Skinner, C. H.; Young, K. M.; Nishi, M. & Langish, S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tritium Decontamination of TFTR D-T Graphite Tiles Employing Ultra Violet Light and a Nd:YAG Laser

Description: The use of an ultra violet (UV) light source (wavelength = 172 nm) and a Nd:YAG Laser for the decontamination of the Tokamak Fusion Test Reactor (TFTR) deuterium-tritium (D-T) tiles will be investigated at the Princeton Plasma Physics Laboratory (PPPL). The development of this form of tritium decontamination may be useful for future D-T burning fusion devices which employ carbon plasma-facing components on the first wall. Carbon tiles retain hydrogen isotopes, and the in-situ tritium decontamin… more
Date: October 1, 1999
Creator: Gentile, C.A.; Skinner, C.H.; Young, K.M.; Ciebiera, L. & al, et
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Periscope-camera system for visible and infrared imaging diagnostics on TFTR

Description: An optical diagnostic consisting of a periscope which relays images of the torus interior to an array of cameras is used on the Tokamak Fusion Test Reactor (TFTR) to view plasma discharge phenomena and inspect vacuum vessel internal structures in both visible and near-infrared wavelength regions. Three periscopes view through 20-cm-diameter fused-silica windows which are spaced around the torus midplane to provide a viewing coverage of approximately 75% of the vacuum vessel internal surface are… more
Date: May 1, 1985
Creator: Medley, S. S.; Dimock, D. L.; Hayes, S.; Long, D.; Lowrence, J. L.; Mastrocola, V. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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TFTR initial operations

Description: The Tokamak Fusion Test Reactor (TFTR) has operated since December 1982 with ohmically heated plasmas. Routine operation with feedback control of plasma current, position, and density has been obtained for plasmas with I/sub p/ approx. = 800 kA, a = 68 cm, R = 250 cm, and B/sub t/ = 27 kG. A maximum plasma current of 1 MA was achieved with q approx. = 2.5. Energy confinement times of approx. 150 msec were measured for hydrogen and deuterium plasmas with anti n/sub e/ approx. = 2 x 10/sup 13/ cm… more
Date: November 1, 1983
Creator: Young, K.M.; Bell, M.; Blanchard, W.R.; Bretz, N.; Cecchi, J.; Coonrod, J. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tritium Removal by Laser Heating and Its Application to Tokamaks

Description: A novel laser heating technique has recently been applied to removing tritium from carbon tiles that had been exposed to deuterium-tritium (DT) plasmas in the Tokamak Test Fusion Reactor (TFTR). A continuous wave neodymium laser, of power up to 300 watts, was used to heat the surface of the tiles. The beam was focused to an intensity, typically 8 kW/cm{sup 2}, and rapidly scanned over the tile surface by galvanometer-driven scanning mirrors. Under the laser irradiation, the surface temperature … more
Date: November 16, 2001
Creator: Skinner, C. H.; Gentile, C. A.; Guttadora, G.; Carpe, A.; Langish, S.; Young, K. M. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Tritium Removal by Laser Heating and Its Application to Tokamaks

Description: A novel laser heating technique has recently been applied to removing tritium from carbon tiles that had been exposed to deuterium-tritium (DT) plasmas in the Tokamak Test Fusion Reactor (TFTR). A continuous wave neodymium laser, of power up to 300 watts, was used to heat the surface of the tiles. The beam was focused to an intensity, typically 8 kW/cm{sup 2}, and rapidly scanned over the tile surface by galvanometer-driven scanning mirrors. Under the laser irradiation, the surface temperature … more
Date: November 16, 2001
Creator: Skinner, C. H.; Gentile, C. A.; Guttadora, G.; Carpe, A.; Langish, S.; Young, K. M. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Tritium Removal by Laser Heating and Its Application to Tokamaks

Description: A novel laser heating technique has recently been applied to removing tritium from carbon tiles that had been exposed to deuterium-tritium (DT) plasmas in the Tokamak Test Fusion Reactor (TFTR). A continuous wave neodymium laser, of power up to 300 watts, was used to heat the surface of the tiles. The beam was focused to an intensity, typically 8 kW/cm{sup 2}, and rapidly scanned over the tile surface by galvanometer-driven scanning mirrors. Under the laser irradiation, the surface temperature … more
Date: November 16, 2001
Creator: Skinner, C. H.; Gentile, C. A.; Guttadora, G.; Carpe, A.; Langish, S.; Young, K. M. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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