Session 9R - Non-Neutral Plasmas II.
POSTER session, Friday morning, November 15
Exhibit Hall - Concourse Level, Adam's Mark
Modelling studies of the Inertial Electrostatic Confinement (IEC)^1 fusion device with D-T fuel have been carried out to determine optimum operational parameters. Results will guide design/operation of IEC devices for near-term low-flux (10^8 n/s) neutron generation, and for planned high-current, high-flux (7*10^12 n/s) devices. Prior calculations of the equilibrium electron temperature and ion upscattering loss rate in a spherically symmetric electrostatic well have been reported.^2-5 The present study extends these analyses using two classes of ions: ``passing'' ions trapped in ``microchannels'' by the accelerating grid field and ``core-confined'' ions trapped in the central plasma core. Q-values are obtained as a function of key parameters.
1. G.H. Miley et al., AIP Conf. Proc. 229, AIP Press, 675-689 (1994). 2. Rider, Phys. Plasmas 2, 1-20 (1995). 3. T.N. Tiouririne, D.C. Barnes, Bult. APS, 40(2), 1665-1666 (1995). 4. W.M. Nevins, Phys. Plasmas 2(10), 3804-3819 (1995). 5. EMC2, Subcontract 9-XG2-Y5957-1 Final Report, Dec. 31, 1994. ^** Supported in part by INEL URC, Contract CC-S-622904-002-C.