Quantitative evaluation of TF ripple loss of DT alpha particles is a central issue for reactor design because of potentially severe first wall heat load problems. DT experiments on TFTR allow experimental measurements to be compared to modeling of the underlying alpha physics, with code validation an important goal. Modeling of TF ripple loss of alphas in TFTR now includes neoclassical calculations of alpha losses arising from first orbit loss, stochastic ripple diffusion, ripple trapping and collisional effects. Recent Hamiltonian coordinate guiding center code (ORBIT) simulations for TFTR have shown that collisions enhance the stochastic TF ripple losses at TFTR. A faster way to simulate experiment has been developed and is discussed here...
The confinement and loss of fusion alpha particles are examined for reversed magnetic shear plasmas ...
MHD-induced increases in alpha particle loss to the wall were observed for both coherent modes and t...
A TFTR supershot with a plasma current of 2.5 MA, neutral beam heating power of 33.7 MW, and a peak ...
Modelling of TF ripple loss of alphas in DT experiments on TFTR now includes neoclassical calculatio...
An experiment was done with TFTR DT plasmas to determine the effect of the q(r) profile on the alpha...
Hamiltonian coordinate, guiding center code calculations of the toroidal field ripple loss of alpha ...
Predictions for ripple loss of fast ions from TFTR are investigated with a guiding center code inclu...
The Pellet Charge Exchange (PCX) diagnostic on the Tokamak Fusion Test Reactor (TFTR) presently meas...
Because alpha particle losses can have a significant influence on tokamak reactor viability, the los...
Measurements of DT alpha particle loss to the outer midplane region of TFTR have been made using a r...
A new code, Monte Carlo Collisional Stochastic Orbit Retracing (MCCSOR), has been developed to model...
The threshold for stochastic transport of high energy trapped particles in a tokamak due to toroidal...
The energy distributions and radial density profiles of the fast-confined trapped alpha particles in...
Princeton's Tokamak Fusion Test Reactor (TFTR) is the first experimental fusion device to routinely ...
An escaping alpha collector probe has been developed for TFTR`s DT phase. Energy distributions of es...
The confinement and loss of fusion alpha particles are examined for reversed magnetic shear plasmas ...
MHD-induced increases in alpha particle loss to the wall were observed for both coherent modes and t...
A TFTR supershot with a plasma current of 2.5 MA, neutral beam heating power of 33.7 MW, and a peak ...
Modelling of TF ripple loss of alphas in DT experiments on TFTR now includes neoclassical calculatio...
An experiment was done with TFTR DT plasmas to determine the effect of the q(r) profile on the alpha...
Hamiltonian coordinate, guiding center code calculations of the toroidal field ripple loss of alpha ...
Predictions for ripple loss of fast ions from TFTR are investigated with a guiding center code inclu...
The Pellet Charge Exchange (PCX) diagnostic on the Tokamak Fusion Test Reactor (TFTR) presently meas...
Because alpha particle losses can have a significant influence on tokamak reactor viability, the los...
Measurements of DT alpha particle loss to the outer midplane region of TFTR have been made using a r...
A new code, Monte Carlo Collisional Stochastic Orbit Retracing (MCCSOR), has been developed to model...
The threshold for stochastic transport of high energy trapped particles in a tokamak due to toroidal...
The energy distributions and radial density profiles of the fast-confined trapped alpha particles in...
Princeton's Tokamak Fusion Test Reactor (TFTR) is the first experimental fusion device to routinely ...
An escaping alpha collector probe has been developed for TFTR`s DT phase. Energy distributions of es...
The confinement and loss of fusion alpha particles are examined for reversed magnetic shear plasmas ...
MHD-induced increases in alpha particle loss to the wall were observed for both coherent modes and t...
A TFTR supershot with a plasma current of 2.5 MA, neutral beam heating power of 33.7 MW, and a peak ...