The heating efficiency of high power (up to 7.2 MW) near-perpendicular neutral beam injection in the PDX tokamak is comparable to that of tangential injection in PLT. Collisionless plasmas with central ion temperatures up to 6.5 keV and central electron temperatures greater than 2.5 keV have been obtained. The plasma pressure, including the contribution from the beam particles, increases with increasing beam power and does not appear to saturate, although the parametric dependence of the energy confinement time is different from that observed in ohmic discharges
The confinement of auxiliary heated NSTX discharges is discussed. The energy confinement time in pla...
Recently, the acceleration voltage of the four ion sources of the second neutral beam injector on th...
Measurements of the gas fueling characteristics of the PDX tokamak have been extended in parameter r...
In 1981, the joint ORNL/PPPL PDX neutral beam heating project succeeded in reliably injecting 7.2 MW...
The PDX divertor configuration has recently been converted from an open to a closed geometry to inhi...
This paper describes the use of novel combined Langmuir-calorimeter probes to measure edge plasma co...
Power transport to the PDX graphite scoop limiter was measured during both ohmic- and neutral-beam-h...
The NCSX (National Compact Stellarator Experiment) has been designed to accommodate a variety of hea...
"Confinement of ripple-trapped energetic ions is studied in a low-aspect-ratio helical system using ...
For a fusion reaction to be feasible, it is necessary to heat plasmas to a very high temperature. On...
Radial transport of ions during co- and counter-neutral beam heating in the PLT tokamak has been stu...
In the Sustained Spheromak Physics Experiment, (SSPX) ['Improved operation of the SSPX spheromak', R...
Plasma heating by injection of high energy neutrals is one of the experiments to be carried out on P...
Neutral beam injection is a very robust tool for heating of high temperature plasmas and is used in ...
SIGLEAvailable from British Library Document Supply Centre- DSC:4672.262(JET-P--92/68) / BLDSC - Bri...
The confinement of auxiliary heated NSTX discharges is discussed. The energy confinement time in pla...
Recently, the acceleration voltage of the four ion sources of the second neutral beam injector on th...
Measurements of the gas fueling characteristics of the PDX tokamak have been extended in parameter r...
In 1981, the joint ORNL/PPPL PDX neutral beam heating project succeeded in reliably injecting 7.2 MW...
The PDX divertor configuration has recently been converted from an open to a closed geometry to inhi...
This paper describes the use of novel combined Langmuir-calorimeter probes to measure edge plasma co...
Power transport to the PDX graphite scoop limiter was measured during both ohmic- and neutral-beam-h...
The NCSX (National Compact Stellarator Experiment) has been designed to accommodate a variety of hea...
"Confinement of ripple-trapped energetic ions is studied in a low-aspect-ratio helical system using ...
For a fusion reaction to be feasible, it is necessary to heat plasmas to a very high temperature. On...
Radial transport of ions during co- and counter-neutral beam heating in the PLT tokamak has been stu...
In the Sustained Spheromak Physics Experiment, (SSPX) ['Improved operation of the SSPX spheromak', R...
Plasma heating by injection of high energy neutrals is one of the experiments to be carried out on P...
Neutral beam injection is a very robust tool for heating of high temperature plasmas and is used in ...
SIGLEAvailable from British Library Document Supply Centre- DSC:4672.262(JET-P--92/68) / BLDSC - Bri...
The confinement of auxiliary heated NSTX discharges is discussed. The energy confinement time in pla...
Recently, the acceleration voltage of the four ion sources of the second neutral beam injector on th...
Measurements of the gas fueling characteristics of the PDX tokamak have been extended in parameter r...