Neutralized, intense-ion beams for fusion

被引:1
|
作者
Wessel, Frank J. [1 ]
Egly, Andrew [1 ]
Rogers, Joel [1 ]
机构
[1] SAFEnergy Inc, Irvine, CA 92602 USA
关键词
intense-ion beam; plasma jet; plasma heating; TRANSVERSE MAGNETIC-FIELD; PULSED-POWER; PLASMA; PROPAGATION; COMPRESSION;
D O I
10.1088/1361-6587/ad3cd0
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
A charge- and current-neutralized, intense-ion beam (IIB) will propagate undeflected in a magnetized plasma by the ExB, or diamagnetic, drift for a distance large compared to the beam-ion gyro-radius. This propagation occurs because of collective plasma effects when the beam-energy density is sufficient to sustain the polarization-electric field, or diamagnetic-screening currents. Our principal interest is the ExB drift, with beta=epsilon(beam)/epsilon(field)<1. IIBs are characterized by parameters in the range: 0.1-2 MeV ion energy, 1-100 MA m(-2) ion-current density, and 17-350 kW average power produced on repetitively-pulsed systems. Multi-MW average-beam power is possible with appropriate modifications to the power supply and ion-source/accelerator. IIBs can be focused geometrically, and/or magnetically, to spot sizes of the order of a few cm's and their angular divergence is typically, similar to 15 mRadians, suitable for long-range propagation in a vacuum beam-line. IIBs lose energy and momentum in the same manner as particles injected by a neutral-beam injector (NBIs), hence could be useful for fusion applications, including: heating, current drive, fueling, profile modifications, etc and such applications have yet to be thoroughly studied. Summarized here are the physical principles accounting for IIB propagation; ion-source designs used to produce the IIB; and pulsed-power methods for energizing the IIB accelerator. This technology base informs scalable metrics for the ion-source/accelerator (excluding the HV power supply and interconnects) used in a conceptual injector that provides the same ion energy and injected power (1 MeV, 17 MW) as NBIs used on ITER. A comparison indicates that the IIB injector would be much smaller in size, lower cost, and have much greater efficiency, while also providing for real-time modulation of the beam energy and intensity and the use of small-diameter injection ports that could minimize fuel contamination and magnetic-field leakage between the IIB injector and tokamak.
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页数:11
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