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  • 1
    Electronic Resource
    Electronic Resource
    [S.l.] : American Institute of Physics (AIP)
    Review of Scientific Instruments 73 (2002), S. 1083-1083 
    ISSN: 1089-7623
    Source: AIP Digital Archive
    Topics: Physics , Electrical Engineering, Measurement and Control Technology
    Notes: Following the withdrawal of the U.S. from the International Thermonuclear Experimental Reactor project, the U.S. Fusion Energy Science program has put increased emphasis on plasma science addressing the fundamental scientific issues facing the realization of fusion energy, with decreased emphasis on long-term fusion technology development, except for that which is needed to support near-term experiments. At the same time, the U.S. fusion program has broadened research from the nearly exclusive development of the Tokamak previously, to include now a variety of smaller-scale alternative fusion approaches, including more work on inertial fusion energy (primarily heavy-ion induction accelerators), Spheromaks, Spherical Tori, Stellerators, reversed field pinches, and field-reversed configurations. The largest U.S. Tokamak, the TFTR at PPPL, has been shut down after achieving over 10 MW of DT fusion power, and is now being decommissioned. The powerful TFTR neutral beams, including the ones that injected 120 keV tritium beams, have been decontaminated and stored for possible future use. One of the TFTR beamlines is being used to power the 1 MA National Spherical Torus Experiment (NSTX) located in what was the nearby TFTR hot-cell room. For heavy-ion fusion, the advent of 100 s, 100 TW table-top lasers has increased interest in using field ionization to achieve controlled levels of high-charge-state heavy ions. © 2002 American Institute of Physics.
    Type of Medium: Electronic Resource
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  • 2
    Electronic Resource
    Electronic Resource
    New York, NY : American Institute of Physics (AIP)
    Physics of Fluids 2 (1990), S. 2941-2960 
    ISSN: 1089-7666
    Source: AIP Digital Archive
    Topics: Physics
    Notes: The physics of enhanced confinement regimes in tokamaks is reviewed and some directions for further enhancements are assessed. The H-mode confinement regime is examined. A number of other observations of enhanced confinement, having in common peaked density profiles, are compared to the theory of ion temperature gradient modes. Two schemes of promise in enhancing confinement, second stability and control of electric fields, are discussed. The contributions of alternate concepts to understanding tokamak transport are described.
    Type of Medium: Electronic Resource
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  • 3
    Electronic Resource
    Electronic Resource
    Springer
    Journal of fusion energy 6 (1987), S. 241-256 
    ISSN: 1572-9591
    Keywords: TIBER ; ETR ; tokamak ; current drive
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract TIBER II is designed to be a minimum size and cost candidate for an international Engineering Test Reactor. High-current density Nb3Sn superconducting magnets with radiation-tolerant polymide insulation is combined with a minimum thickness tungsten inbored shield and a common, external vacuum boundary to minimize the inner radial build of the tokamak core. This results in a major radius of 3 m, compared to 5 m for previous ETR designs such as INTOR, with correspondingly lower costs expected. Cyclic stress fatigue limits the number of pulses so that steady-state current drive, based on a combination of neutral beams, lower hybrid and ECH, is designed to achieve reactor-relevant nuclear testing conditions (Fluence ⩾ 3MW yr/m2, rwall 〉 1 MW/m2 in steady state).
    Type of Medium: Electronic Resource
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  • 4
    ISSN: 1572-9591
    Keywords: Fusion materials ; materials development ; neutron damage ; neutron source
    Source: Springer Online Journal Archives 1860-2000
    Topics: Energy, Environment Protection, Nuclear Power Engineering
    Notes: Abstract The design and performance of a relatively low-cost, plasma-based, 14-MeV D-T neutron source for accelerated end-of-life testing of fusion reactor materials are described in this article. An intense flux (up to 5×1018 n/m2·s) of 14-MeV neutrons is produced in a fully-ionized high-density tritium target (n e ≈ 3×1021 m−3) by injecting a current of 150-keV deuterium atoms. The tritium plasma target and the energetic D+ density produced by D0 injection are confined in a column of diameter ⩽ 0.16 m by a linear magnet set, which provides magnetic fields up to 12 T. Energy deposited by transverse injection of neutral beams at the midpoint of the column is conducted along the plasma column to the end regions. Longitudinal plasma pressure in the column is balanced by neutral gas pressure in the end tanks. The target plasma temperature is about 200 eV at the beam-injection position and falls to 5 eV or less in the end region. Ions reach the walls with energies below the sputtering threshold, and the wall temperature is maintained below 740 K by conventional cooling technology.
    Type of Medium: Electronic Resource
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