The coupling of stimulated Raman and Brillouin scattering in a plasma

The observation of an anti-Stokes satellite in the spectrum of light backscattered from a CO2 laser plasma is reported. Its origin is found to be Thomson scattering of the incident light from a counterpropagating mode-coupled plasma wave. The parent electron and ion waves in the mode-coupling process were driven by stimulated Raman and Brillouin backscattering. The parent and daughter plasma waves were detected by ruby laser Thomson scattering. A computer simulation modeling the experiment shows further cascading of the Stokes backscattered light to lower frequencies, apparently a result of its rescattering from another, higher phase velocity, counterpropagating coupled mode. Comparisons with theoretical predictions are presented

Calculations of alpha particle loss for reversed magnetic shear in the Tokamak Fusion Test Reactor

Hamiltonian coordinate, guiding center code calculations of the toroidal field ripple loss of alpha particles from a reversed shear plasma predict both total alpha losses and ripple diffusion losses to be greater than those from a comparable non-reversed magnetic shear plasma in the Tokamak Fusion Test Reactor (TFTR) [Fusion Technol. 21, 1324 (1992)]. High central q is found to increase alpha ripple losses as well as first orbit losses of alphas in the reversed shear simulations. A simple ripple loss model, benchmarked against the guiding center code, is found to work satisfactorily in transport analysis modelling of reversed and monotonic shear scenarios. Alpha ripple transport on TFTR affects ions within r/a=0.5, not at the plasma edge. The entire plasma is above threshold for stochastic ripple loss of alpha particles at birth energy in the reversed shear case simulated, so that all trapped 3.5 MeV alphas are lost stochastically or through prompt losses. The 40% alpha particle loss predictions for TFTR suggest that reduction of toroidal field ripple will be a critical issue in the design of a reversed shear fusion reactor

Neoclassical Simulations of Fusion Alpha Particles in Pellet Charge Exchange Experiments on the Tokamak Fusion Test Reactor

Neoclassical simulations of alpha particle density profiles in high fusion power plasmas on the Tokamak Fusion Test Reactor (TFTR) [Phys. Plasmas 5 (1998) 1577] are found to be in good agreement with measurements of the alpha distribution function made with a sensitive active neutral particle diagnostic. The calculations are carried out in Hamiltonian magnetic coordinates with a fast, particle-following Monte Carlo code which includes the neoclassical transport processes, a recent first-principles model for stochastic ripple loss and collisional effects. New global loss and confinement domain calculations allow an estimate of the actual alpha particle densities measured with the pellet charge exchange diagnostic

Calculations of alpha particle loss for reversed magnetic shear in the Tokamak Fusion Test Reactor

Hamiltonian coordinate, guiding center code calculations of the toroidal field ripple loss of alpha particles from a reversed shear plasma predict both total alpha losses and ripple diffusion losses to be greater than those from a comparable non-reversed magnetic shear plasma in the Tokamak Fusion Test Reactor (TFTR) [Fusion Technol. 21, 1324 (1992)]. High central q is found to increase alpha ripple losses as well as first orbit losses of alphas in the reversed shear simulations. A simple ripple loss model, benchmarked against the guiding center code, is found to work satisfactorily in transport analysis modelling of reversed and monotonic shear scenarios. Alpha ripple transport on TFTR affects ions within r/a=0.5, not at the plasma edge. The entire plasma is above threshold for stochastic ripple loss of alpha particles at birth energy in the reversed shear case simulated, so that all trapped 3.5 MeV alphas are lost stochastically or through prompt losses. The 40% alpha particle loss predictions for TFTR suggest that reduction of toroidal field ripple will be a critical issue in the design of a reversed shear fusion reactor

Calculations of double cylinder implosions at OMEGA

Foam-filled double cylinder targets have been imploded by the OMEGA laser at the University of Rochester. A marker layer of heavier material is placed between the foam and the outside ablator. The marker layer is hydrodynamically unstable when a strong shock passes through both these interfaces and the marker layer material mixes into the foam and the ablator. These experiments thus measure mix in the compressible, convergent, miscible, strong-shock regime. With double cylinder targets, the initial shock converges on the central cylinder and then rebounds and expands. The shock is predicted to create even more mixing of the marker layer as it traverses the previously mixed region. The strength of the reflected shock can be varied by changing the materials in the inner cylinder. Calculations of these implosions using the AMR code, RAGE, are presented for the several target designs. The 2-d calculations give the hydrodynamic evolution of the implosion, shock timings, and the growth of the mix width. The calculations include the effects of surface roughness in the marker layer. Simulated radiographs of the cylindrical implosions are also shown

Disruptions in the TFTR tokamak

For a successful reactor, it will be useful to predict the occurrence of disruptions and to understand disruption effects including how a plasma disrupts onto the wall and how reproducibly it does so. Studies of disruptions on TFTR at both high-[beta][sub pol] and high-density have shown that, in both types, a fast growing m/n=1/1 mode plays an important role. In highdensity disruptions, a newly observed fast m/n = 1/1 mode occurs early in the thermal decay phase. For the first time in TFTR q-profile measurements just prior to disruptions have been made. Experimental studies of heat deposition patterns on the first wall of TFTR due to disruptions have provided information on MHD phenomena prior to or during the disruption, how the energy is released to the wall, and the reproducibility of the heat loads from disruptions. This information is important in the design of future devices such as ITER. Several new processes of runaway electron generation are theoretically suggested and their application to TFTR and ITER is considered, together with a preliminary assessment of x-ray data from runaways generated during disruptions

TRANSPORT PHYSICS IN REVERSED SHEAR PLASMAS

Abstract TRANSPORT PHYSICS IN REVERSED SHEAR PLASMAS. Rcversed magnetic shear is considered a good candidate for improving the tokamak c m q t because it has the potcntial to stabilize MHD instabilities and reduce panicle and energy transport. With reduced transpon. the high ptessun gradient would generate a strong off-axis bootstrap current and could sustain a hollow current density profile. Such a conlbination of favorable conditions cwld lead to an attractive steady-state tokamak configuntion. Indeed, a new tokamak confinement regime with reversed magnetic shear has been cbserved on the Tokamak Fusion Test Reactor (TFTR) where the panicle. mOnienNm. &,ion thermal diffusiviticr drop precipitously, by Over an order of magnitude. ?he panicle diffusivity drops to the neoclassical level and the ion thermal diffisivity drops to much less than the neoclassical value in the region with mend shear. This enhanced reversed shear CERS) confinement mode is characterized by an abmpt tmsition with P large rate of rise of the density in the reversed shear region dur!ng neutral beam injection. resulting in nearly a factor of three increase in the ccntral density to -1.2 x 10" ni-'. At thc smie time thc density fluctuation levfl in the reversed shcar region dramatically decreases. The ion and clcctron temperatures, which are about 20 keV and 7 keV respectively, change little during the ERS mode. Thc transport and transition into and out of the ERS mode have been studied on TFTR with plasma currcnts in the range 0.9-2.2 MA, with a toroidal magnetic field of 2.7-4.6 T. and the radius of thc q(r) mininium. qmb, has been varied from do = 0.35 to 0.55. Toroidal field and co/counter neutral beam injection toroidal rotation variations have been used to elucidate the underlying physics of the transition mcchanism and power threshold of the ERS mode. 19980330 097 31