Alpha-CHERS: A spectroscopic experiment to detect nonthermal alpha particles on TFTR

The α-CHERS diagnostic is a high throughput charge exchange recombination spectroscopy diagnostic designed to measure the density profile and time evolution of 0–500 keV alpha particles during D–T operation of the Tokamak Fusion Test Reactor (TFTR). Following successful tests with a prototype α-CHERS system, an improved, multichannel system has been installed for D–T operation. Three spatial channels may be observed simultaneously, and the spectral resolution of 0.5 nm permits increased alpha energy resolution and improved impurity line identification. More efficient coupling optics between the spectrometer and charge coupled device (CCD) detectors have increased the light throughput, and radiation shielding has been installed around the detectors and spectrometers to eliminate the neutron/gamma-ray noise observed in high power D–D plasmas.

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Implementation of the α-CHERS diagnostic for D–T operation of TFTR

McKee

Fonck

Thorson

et al. 1995

Review of Scientific Instruments

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An inversion technique to obtain full poloidal velocity profiles in a tokamak plasma

Bell

1997

Review of Scientific Instruments

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An inversion technique has been developed to calculate local poloidal rotation velocities of impurity ions from line-integrated measurements of an extended emission source in a tokamak plasma. This technique can recover radial spatial resolution that is lost due to the curvature of the field lines. With charge exchange emission from neutral beams, it can be used to obtain poloidal velocity profiles across the entire minor radius of the plasma without requiring restricted neutral beam height to localize the emission. The technique consists of two Abel-like matrix inversions to obtain the emissivity and the velocity-weighted emissivity from which the velocity is obtained. Use of the neutral beams breaks the assumed symmetry, but knowledge of the beam deposition and geometry allow analogous matrices to be generated. The inversion technique is demonstrated with a simulation of a poloidal rotation diagnostic for the TFTR tokamak with tangential neutral beams with a height of 80 cm. Two opposing vertical views are required to handle effects of the charge exchange cross section, which can cause apparent velocities greatly in excess of expected poloidal velocities. The simulated errors due to the inversion process are about 1.5 km/s near the plasma center.

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Preparations for deuterium–tritium experiments on the Tokamak Fusion Test Reactor*

et al. 1994

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The final hardware modifications for tritium operation have been completed for the Tokamak Fusion Test Reactor (TFTR) [Fusion Techno!. 21, 1324]. These activities include preparation of the tritium gas handling system, installation of additional neutron shielding, conversion of the toroidal field coil cooling system from water to a Fluorinert TM system, modification of the vacuum system to handle tritium, preparation, and testing of the neutral beam system for tritium operation and a final deuterium-deuterium (D-D) run to simulate expected deuterium-tritium (D-T) operation. Testing of the tritium system with low concentration tritium has successfully begun. Simulation of trace and high power D-T experiments using D-D have been performed. The physics objectives of D-T operation are production of::::; 10 MW of fusion power, evaluation of confinement, and heating in deuteriumtritium plasmas, evaluation of a-particle heating of electrons, and collective effects driven by alpha particles and testing of diagnostics for confined a particles. Experimental results and theoretical modeling in support of the D-T experiments are reviewed.

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Alpha-CHERS: A spectroscopic experiment to detect nonthermal alpha particles on TFTR

Cited by 8 publications

References 5 publications

Implementation of the α-CHERS diagnostic for D–T operation of TFTR

Implementation of the α-CHERS diagnostic for D–T operation of TFTR

An inversion technique to obtain full poloidal velocity profiles in a tokamak plasma

Preparations for deuterium–tritium experiments on the Tokamak Fusion Test Reactor*

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