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  • 1
    Electronic Resource
    Electronic Resource
    [S.l.] : American Institute of Physics (AIP)
    Physics of Plasmas 7 (2000), S. 957-962 
    ISSN: 1089-7674
    Source: AIP Digital Archive
    Topics: Physics
    Notes: This paper reports first observations in a tokamak plasma of MeV energy ions produced by close elastic collisions (knock-on) between deuterium–tritium fusion α-particles and thermal plasma fuel ions. Measurements of flux of MeV energy helium and deuterium atoms from the plasma in the Joint European Torus [P.-H. Rebut, A. Gibson, M. Huget et al., Nucl. Fusion 32, 187 (1992)] were made from which line-integrated energy distribution function of knock-on deuterons, F¯d(E), was deduced. Neutralization of the deuterons and α-particles was effected by charge-exchange with one- and two-electron species of the main intrinsic plasma impurities, carbon, beryllium, and helium. Deduced F¯d(E) is shown to be in agreement with calculations using classical confinement and slowing-down of fusion α-particles and knock-on deuterons. © 2000 American Institute of Physics.
    Type of Medium: Electronic Resource
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  • 2
    Electronic Resource
    Electronic Resource
    [S.l.] : American Institute of Physics (AIP)
    Physics of Plasmas 4 (1997), S. 3667-3675 
    ISSN: 1089-7674
    Source: AIP Digital Archive
    Topics: Physics
    Notes: The trajectories of neutral beam injected energetic ions in spherical tokamaks are examined. The large poloidal magnetic field in the outboard region of spherical tokamaks causes neutral beam injected ions to be born on trapped orbits even with cotangential injection. Numerical solutions to the equations for particle motion and for guiding center drifts are compared in several magnetic equilibria for a range of particle initial conditions. Even when rL/a∼1/4 the guiding center orbits closely resemble the path of the instantaneous center of gyration of the particle motion; exceptions occur primarily for orbits near the trapped/passing boundary. Finite Larmor radius effects are included in guiding center simulations of prompt orbit loss in the National Spherical Tokamak Experiment (NSTX) [J. Spitzer et al., Fusion Technol. 30, 1337 (1996)]. Orbit loss in the NSTX is caused primarily by collisions with the close fitting conducting shell, and severe losses would be expected with counter directed injection. While most orbits are similar to those found in conventional tokamaks, additional orbit types are possible in spherical tokamaks. © 1997 American Institute of Physics.
    Type of Medium: Electronic Resource
    Library Location Call Number Volume/Issue/Year Availability
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