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Fusion Research Center

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Now showing 1 - 7 of 7
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    Higher Order Approximations of the TEP Method for Neutral Particle Transport in Edge Plasmas
    (Georgia Institute of Technology, 2006) Stacey, Weston M. ; Zhang, Dingkang ; Mandrekas, John
    Higher order approximations, which take into account the effects of angular anisotropy, spatial non-uniformity and energy dependence of the distribution of neutral particles, have been developed and implemented to extend the range of validity of the Transmission and Escape Probabilities (TEP) method for the calculation of neutral particle transport in plasmas. Comparisons with Monte Carlo calculations of model test problems and DIII-D L- and H- mode discharges show that these new extensions significantly improve the accuracy and extend the range of validity of the TEP methodology.
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    A neoclassical calculation of toroidal rotation profiles and comparison with DIII-D measurements
    (Georgia Institute of Technology, 2006) Stacey, Weston M. ; Johnson, R. W. ; Mandrekas, John
    Momentum and particle balance and neoclassical viscosity were applied to calculate the radial profile of toroidal rotation velocity in several DIII-D [J. Luxon, Nucl. Fusion, 42, 614 (2002)] discharges in a variety of energy confinement regimes (Lowmode, Low-mode with Internal Transport Barrier, High-mode, and High-mode with Quiescent Double Barrier). Calculated toroidal rotation velocities generally were found to (over-) predict measured values to well within a factor of 2.
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    Sub-critical Transmutation Reactors with Tokamak Fusion Neutron Sources
    (Georgia Institute of Technology, 2005) Stacey, Weston M. ; Mandrekas, John ; Hoffman, E. A. (Elisha Albright)
    The principal results of a series of design scoping studies of sub-critical fast transmutation reactors (based on the nuclear and processing technology being developed in the USDoE Generation IV, Advanced Fuel Cycle and Next Generation Nuclear Plant programs) coupled with a tokamak fusion neutron source (based on the ITER design basis physics and technology) are presented.
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    Extensions of the TEP Neutral Transport Methodology
    (Georgia Institute of Technology, 2004-04) Stacey, Weston M. ; Zhang, Dingkang ; Mandrekas, John
    Recent extensions of the Transmission and Escape Probability methodology and its implementation in the 2-D neutral transport code GTNEUT are presented. These extensions address the issues of anisotropy of the neutral distribution function at the interfaces and the non-uniformity of the first collision source in short mean free path regions. Comparisons with Monte Carlo for a number of model problems are discussed.
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    A Superconducting Tokamak Fusion Transmutation of Waste Reactor
    (Georgia Institute of Technology, 2004-01) Stacey, Weston M. ; Mauer, A. N. ; Mandrekas, John ; Hoffman, E. A. (Elisha Albright)
    We are developing a Fusion Transmutation of Waste Reactor (FTWR) concept—a sub-critical, metal fuel, liquid metal cooled fast reactor driven by a tokamak DT fusion neutron source. An emphasis is placed on using nuclear, separation/processing and fusion technologies that either exist or are at an advanced state of development and on using plasma physics parameters that are supported by the existing database. We have previously discussed the general capabilities of DT tokamak neutron sources for driving transmutation reactors [1] and developed a design concept for a FTWR [2] based on normal conducting magnets. The concept has been further developed in papers dealing with nuclear design and safety [3] and with the evaluation of the potential impact on radioactive waste management [4]. The purpose of this paper is to examine how the FTWR design concept would change if superconducting magnets were used.
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    A Fusion Transmutation of Waste Reactor
    (Georgia Institute of Technology, 2002-03) Stacey, Weston M. ; Mandrekas, John ; Hoffman, E. A. (Elisha Albright) ; Kessler, G. P. ; Kirby, C. M. ; Mauer, A. N. ; Noble, J. J. ; Stopp, D. M. ; Ulevich, D. S.
    A design concept and the performance characteristics for a fusion transmutation of waste reactor (FTWR)—a sub-critical fast reactor driven by a tokamak fusion neutron source--are presented. The present design concept is based on nuclear, processing and fusion technologies that either exist or are at an advanced stage of development and on the existing tokamak plasma physics database. A FTWR, operating with k[subscript eff] ≤ 0.95 at a thermal power output of about 3 GW and with a fusion neutron source operating at Q [subscript p] = 1.5-2, could fission the transuranic content of about a hundred metric tons of spent nuclear fuel per full-power-year and would be self-sufficient in both electricity and tritium production. In equilibrium, a nuclear fleet consisting of LWRs and FTWRs in the electrical power ratio of 3/1 would reduce the actinides discharged from the LWRs in a once-through fuel cycle by 99.4% in the waste stream that must be stored in high-level waste repositories.
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    Comparison of neoclassical rotation theory with experiment under a variety of conditions in DIII-D
    (Georgia Institute of Technology, 2002-03) Stacey, Weston M. ; Mandrekas, John
    A neoclassical theory of gyroviscous radial momentum transport and poloidal and toroidal rotation has been compared with experiment in DIII-D discharges in different confinement regimes, with a range of neutral beam powers and with co- and counter-injection, and with various types of dominant impurity species present. Calculated central toroidal rotation velocities and momentum confinement times agreed with experiment over a wide range of these conditions, with one notable exception in which a drift correction may be needed to reduce the gyroviscous toroidal force. Radial distributions of toroidal rotation velocities and radial electric field, calculated using the radial distribution of toroidal angular momentum input density, agreed with measured distributions.