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  1. Testing of ITER prototype cable-in-conduit conductors in the FENIX facility [electronic resource].

    Washington, D.C. : United States. Dept. of Energy. ; Oak Ridge, Tenn. : distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1993

    The Fusion Engineering International experiment (FENIX) Test Facility has been operational since 1991 at the Lawrence Livermore National Laboratory for testing the International Thermonuclear Experimental Reactor (ITER) prototype conductors. These conductors are designed to operate stably with transport current of more than 40 kA at a magnetic field of 13 T. The FENIX facility consists of four magnet sets that are configured to allow easy access to the 40-cm high-field region with a test cross-section area of 10 * 15 cm². FENIX provides test conditions that closely simulate the ITER magnet operation mode. Performed experiments Include measurements of critical current, current-sharing temperature, forced-flow properties, stability, joint performance and cyclic fatigue effects. This paper describes the design and performance of these experiments.

    Online OSTI

  2. Wide-angle ITER-Prototype tangential IR and visibleviewing system for DIII-Da [electronic resource]

    Washington, D.C. : United States. Dept. of Energy. ; Oak Ridge, Tenn. : distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 2014

    Abstract not provided

    Online OSTI

  3. Wide-angle ITER-prototype tangential infrared and visible viewing system for DIII-D [electronic resource].

    Washington, D.C. : United States. Office of the Assistant Secretary for Nuclear Energy ; Oak Ridge, Tenn. : distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 2014

    An imaging system with a wide-angle tangential view of the full poloidal cross-section of the tokamak in simultaneous infrared and visible light has been installed on DIII-D. The optical train includes three polished stainless steel mirrors in vacuum, which view the tokamak through an aperture in the first mirror, similar to the design concept proposed for ITER. A dichroic beam splitter outside the vacuum separates visible and infrared (IR) light. Spatial calibration is accomplished by warping a CAD-rendered image to align with landmarks in a data image. The IR camera provides scrape-off layer heat flux profile deposition features in diverted and inner-wall-limited plasmas, such as heat flux reduction in pumped radiative divertor shots. As a result, demonstration of the system to date includes observation of fast-ion losses to the outer wall during neutral beam injection, and shows reduced peak wall heat loading with disruption mitigation by injection of a massive gas puff.

    Online OSTI

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