The reactor performance is considered for intensely beam-driven tokamak plasmas with 50:50 D-T composition maintained by neutral-beam injection of both D and T, together with plasma recycling. The D and T are injected with equal intensity and velocity. This mode of operation is most appropriate for high-duty- factor, high-power-density operation, in the absence of pellet injection. The isotropic velocity distributions of energetic D and T ions (for multi-angle injection) are calculated from a simple slowing-down model, but include a tail above the injection velocity. The neutron source characteristics are determined from fusion reactivities calculated for beam-target, hot-ion, and thermonuclear reactions. For conditions where Q approximates...
The neutral-beam injection requirements for heating and fueling the next generation of fusion reacto...
Neutral-beam heating of plasmas in the Tokamak Fusion Test Reactor at low preinjection densities [ne...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...
We report measurements of the fusion reaction rate in the Tokamak Fusion Test Reactor (TFTR) coverin...
A tokamak neutron source that produces a neutron flux approximately 10$sup 13$ n/cm$sup 2$/s over a ...
The hypothesis that the heating beam fueling profile shape connects the edge condition and improved ...
A conceptual design of a D-T fusion facility for continuous production of 14-MeV neutron wall loadin...
The high performance regimes achieved in JT-60U and TFTR have produced peak DD fusion neutron rates ...
Scalings for the stored energy and neutron yield, determined from experimental data are applied to b...
Neutral beam injection is supposed to be the main source of high-energy particles, driving non-induc...
From topical meeting on technology of controlled nuclear fusion; San Diego, California, USA (16 Apr ...
Various DD and DT plasmas are analysed for effects of fast ion transport with a time dependent, 1 1/...
The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facilit...
Neutron measurements during injection of deuterium pellets into deuterium plasmas on the tokamak fus...
Adiabatic toroidal compression experiments were performed in conjunction with high power neutral bea...
The neutral-beam injection requirements for heating and fueling the next generation of fusion reacto...
Neutral-beam heating of plasmas in the Tokamak Fusion Test Reactor at low preinjection densities [ne...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...
We report measurements of the fusion reaction rate in the Tokamak Fusion Test Reactor (TFTR) coverin...
A tokamak neutron source that produces a neutron flux approximately 10$sup 13$ n/cm$sup 2$/s over a ...
The hypothesis that the heating beam fueling profile shape connects the edge condition and improved ...
A conceptual design of a D-T fusion facility for continuous production of 14-MeV neutron wall loadin...
The high performance regimes achieved in JT-60U and TFTR have produced peak DD fusion neutron rates ...
Scalings for the stored energy and neutron yield, determined from experimental data are applied to b...
Neutral beam injection is supposed to be the main source of high-energy particles, driving non-induc...
From topical meeting on technology of controlled nuclear fusion; San Diego, California, USA (16 Apr ...
Various DD and DT plasmas are analysed for effects of fast ion transport with a time dependent, 1 1/...
The Tokamak Fusion Test Reactor will be installed at the Princeton Plasma Physics Laboratory facilit...
Neutron measurements during injection of deuterium pellets into deuterium plasmas on the tokamak fus...
Adiabatic toroidal compression experiments were performed in conjunction with high power neutral bea...
The neutral-beam injection requirements for heating and fueling the next generation of fusion reacto...
Neutral-beam heating of plasmas in the Tokamak Fusion Test Reactor at low preinjection densities [ne...
From 5th symposium on engineering problems of fusion research; Princeton, New Jersey, USA (6 Nov 197...