Alexei Pankin:   

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Current Researches:
A model for the H-mode pedestal and type I ELMs, which is based on the magnetic and ExB shear reduction of anomalous transport, is introduced. The model takes into account the fact that different modes are suppressed at different rate. The model is used in an integrated transport code to follow the time evolution of tokamak discharges from the Ohmic stage through the transition from L-mode to H-mode to the formation of the H-mode pedestal and the triggering of ELMs. The model predicts the width and height of the H-mode pedestal and the frequency of ELM. Two mechanisms for triggering ELMs are considered. The ELMs can be triggered by the ballooning modes if the pressure gradient exceeds the ballooning limit, ac, or by peeling modes if the edge current density exceeds the peeling condition. Suppression of the anomalous transport within the pedestal region enhances the role on neoclassical transport in this region. Several models for the neoclassical transport are tested together with the combined model for ELMs and H-mode pedestal. The dependencies of pedestal temperature, pedestal width, and frequency of ELMs as a function heating power, magnetic field, and pedestal density are discussed (more details are here).

News:

Development of the new module for drift Alfvén modes from Bruce Scott turbulence simulations

Alcator C-Mod paper is submitted to the Physics of Plasmas

D3d NEON 98775 with new version of GLF23 code.

 

Comparison of the NTCC demo code with XPTOR results for TFTR 50911.

 

Testing D3D 81499, D3DNEON 98777, JET 35171 shots with GLF23, IFS/PPPL, and Multi-Mode Model in the framework of the NTCC Demo Projects.

 

Predictive modeling of Alcator C-Mod discharge with 1 and 1/2 transport BALDUR code.


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Evaluation of Models for L-H Transition

A model for the transition from L-mode to H-mode is required for use in predictive integrated modeling codes in order to simulate the time dependence of tokamak discharges that include the L-H transition. In order to develop and test a model for the L-H transition, two theories for the transition are analyzed and the resulting criteria for the transition are compared. One theory considered is based on the stabilization of a strongly ballooning resistive mode by the ion diamagnetic drift [J. Weiland et al., in Proc. of the 17th IAEA Int. Conference (Yokohama, Japan, October 1998) 4 1537]. This theory provides the condition for the L-H transition in terms of hi=Ln/LT (where Ln is the density scale length and LT is the temperature scale length) and indicates that the transition to H-mode can occur without toroidal rotation, when the ion temperature gradients are sufficiently steep at the edge of the plasma. The second L-H theory is based on the idea of the generation of flow shear by finite β drift waves [P. N. Guzdar et al., Phys. Rev. Lett. 89 265004 (2002)]. In this case, the criterion for L-H transition is expressed in the terms of electron temperature. This criterion depends on the electron density gradients, but does not depend on the ion or electron temperature gradients. To test the latter theory, an analytical expression for the critical value of electron temperature is employed in the BALDUR code. The critical electron temperature depends on the global plasma parameters such as major radius, toroidal magnetic field, and effective impurity content. Discharges with a variety of values of these parameters are considered in order to form systematic scans and to test the model in the different operational regimes. Also implemented in the BALDUR code is an empirical model in which the condition for
the L-H transition is expressed in terms of a critical value for the heating power [Y. Shimomura et al. Nuclear Fusion 41 309 (2001)]. The theory model based on flow shear and the empirical model are tested against each other and against experimental data from the Alcator C-Mod, DIII-D, and JET tokamaks. Simulation results obtained with the theory-based model and some experimental observations suggest that
edge plasma profile gradients are responsible for the L-H transition.

NUBEAM module for Neutral Beam Injection heating

The NUBEAM module is a comprehensive computational model for Neutral Beam Injection (NBI) in tokamaks. It is used to compute power deposition, driven current, momentum transfer, fueling, and other profiles in tokamak plasmas due to NBI. NUBEAM computes the time-dependent deposition and slowing down of the fast ions produced by NBI, taking into consideration beam geometry and composition, ion-neutral interactions (atomic physics), anomalous diffusion of fast ions, the effects of large scale instabilities, the effect of magnetic ripple, and finite Larmor radius effects. The NUBEAM module can also treat fusion product ions that contribute to alpha heating and ash accumulation, whether or not NBI is present. These physical phenomena are important in simulations of present day tokamaks and projections to future devices such as ITER. The NUBEAM module was extracted from the TRANSP integrated modeling code, using standards of the National Transport Code Collaboration (NTCC), and was submitted to the NTCC module library. Numerical techniques that are used for computing the Neutral Beam Injection (NBI) physics used in several integrated modeling codes are compared. The Monte-Carlo NUBEAM module and the Fokker-Planck NBI ASTRA, DBEAMS, FPP, and NBEAMS neutral beam injection modules are considered. Physics included in these modules is discussed. Resulting electron and ion power heating profiles and particle source profiles for the TFTR discharge 66887 and the JET discharge 52009 are compared when computed with the NUBEAM, NBI ASTRA, DBEAMS and FPP modules.

Toroidal ETG mode structure in the presence of nonuniform background flows

The influence of nonuniform poloidal and toroidal background plasma flows on the spatial structure and growth rate of the electrostatic Electron Temperature Gradient (ETG) mode is investigated in the linear approximation. This derivation includes the ballooning mode formalism and a more recently developed version of the direct method by Taylor and Wilson [Plasma Physics and Control. Fusion 38 1999 (1996)]. It is shown that the growth rate of the ETG mode is not changed significantly by flow shear. However, it is found that the spatial structure of the ETG mode depends crucially on the derivative of the flow shear rate with respect to the minor radius of the tokamak cross section and also depends crucially on the magnetic shear. For moderate magnetic shear, the unstable ETG mode is strongly localized in the poloidal direction and is elongated along the radial direction, with a characteristic radial width much larger than the electron Larmor radius. This may explain the formation of streamer structures above the threshold of ETG mode instability. Streamers are believed to enhance electron thermal transport beyond the values provided by simple mixing length estimates. For very low values of magnetic shear, the ETG mode structure becomes extended in the poloidal direction, and the ballooning formalism does not apply. In this case, the direct method is used and it is shown that the ETG mode is strongly localized in the radial direction. The small radial extent of these modes may considerably reduce electron heat transport, which would enhance the formation of an electron thermal transport barrier.

Simulation of Alcator C-Mod discharges

Predictive simulations for the Alcator C-mod tokamak [I. Hutchinson et al., Phys. Plasmas 1 1511 (1994)] are carried out using the BALDUR integrated modeling code [C.E. Singer et al., Comp. Phys. Comm. 49 275 (1988)]. The results are obtained for temperature and density profiles using the Multi-Mode transport model [G. Bateman et al., Phys. Plasmas 5 1793 (1998)] as well as the mixed-Bohm/gyro-Bohm transport model [M.~Erba et al., Plasma Phys. Control. Fusion 39 261 (1997)]. The simulated discharges are characterized by very high plasma density in both low and high modes of confinement. The predicted profiles for each of the transport models match the experimental data about equally well in spite of the fact that the two models have different dimensionless scalings. Average relative rms deviations are less than 8\% for the electron density profiles and 16 % for the electron and ion temperature profiles.

ITG fluid model near boundary of marginal stability

The ion­temperature-gradient driven modes (hi-modes) along with the trapped electron mode and pressure gradient ballooning modes are dominating instabilities for the most realistic tokamak parameters (low b and weak collisionality) and in many cases are responsible for anomalous ion transport in tokamak plasmas. As a graduate student of Prof. Davydova I took part in the development of the hi-mode fluid model in slab and toroidal geometry near the boundary of marginal stability. This approach allowed to elucidate the problem of subcritical turbulence of strong reactive unstable modes such as the ion-temperature-gradient driven modes are. Our particular attention has been focused on the possibility of soliton and vortex formation, which are the structure elements of turbulence. The turbulent state arises from interactions (collisions) of these structures. Besides, formation of coherent long-lived large-scale structures of drift modes is sometimes considered to be one of the main reasons of transition to the regime of improved confinement in tokamaks (L-H transition) and sometimes as the reason for anomalous transport.

TAE instability

One of the major issues in a-particle physics of tokamaks is the low n toroidicity-induced Alfven eigenmode (TAE) instability driven by a-particle pressure gradient and the resultant a-particle transport. The main results of the previous studies of this problem are that the volume averaged a-particle beta threshold for TAE instability is small and is on the order of 10-4, and that for relatively low fluctuation level with (dBr/B0)³10-4 the a-particle loss time is comparable and even shorter than the a-particle slowing-down time. That is why the problem of efficient suppression of this instability seems to be important. We have considered an alternative damping mechanism, which should arise in the stationary tokamak reactor, when the plasma current is driven by lower hybrid (LH) waves, which is the most perspective current drive scheme at present.

Precessional current in ECR heated plasma

Electron cyclotron resonance (ECR) heating in a tokamak can produce superthermal runaway electrons having their turning points located at the cyclotron resonance surface (so called ''sloshing'' electrons). The drift motion causes these trapped hot electrons to precess around the torus, thus forming a hot electron current. A semi-analytic model has been used to calculate the direction, magnitude and profile of this current. For typical high power central ECR heating, a hot electron current density of j||~140A/cm2 is found which is peaked at a radius ~ RF power deposition where it enhances the local current density. The effect of the hot electron current is to flatten the q-profile within the RF power deposition region. If this radius is comparable with q=1 radius, this results in sawtooth stabilization. Moreover, low magnetic shear is favourable for hot current filaments formation, which was observed in experiment.

Explosive Instability

Non-equilibrium media can relax toward equilibrium by a nonlinear instability, which involves the interaction of many waves either with each other or with particles. One of the most interesting examples of this is the explosive instability. The instability develops if at least one of resonantly interacting waves is a “negative” or “zero-energy” wave. The last case gives an especially efficient channel of realignment or relaxation of the energy in plasma, fluid, and electronic beam systems. We found that account for the boundedness of the wave interaction region due either to the inhomogeneity of the media, leading to detuning of the wave phases, or to the boundedness of the system may affect the explosive instability dynamics. In this case the modified explosive instability is saturated at sufficiently lower wave amplitudes if unstable perturbations escape from the interaction region in a smaller time than the “explosion time”. This conclusion has been predicted theoretically and then proved numerically.

Diffusion process in plasma arcs

Plasma arc is a commonly used tool of modern technologies. Transport processes determine substantially the characteristics of the arcs. The commonly used assumption that gives a basis for the most recent models of free burning arc is the local thermal equilibrium (LTE). The problem of applicability of the assumption is typically out of consideration, while it is known a number of cases where LTE does not work. We have elaborated an analytical model of free burning arc plasma, which takes into account two factors to be considered as major reasons of the deviation from the LTE: diffusion and radiation transfer. We have analyzed both factors and built a numerical model of an electric arc with melting copper electrodes. It has been shown that prevalent mechanism in many cases is resonant radiation transfer. The developed model allows determining the spatial distributions of partial concentrations in multi-component arc plasmas and could be used for optimization of welding processes. The results have been reported on the national and international conferences, in technical reports, and in articles [1, 12]. I took active part in different stages of the studies. In particular, I have developed analytical and numerical models of the diffusive processes in the free-burning arc with melted copper electrodes.

Monte-Carlo modeling of abnormal glow discharges

Abnormal glow discharges are a commonly used tool to achieve the technological objectives, such as ion implantation or fast etching by intensive ion flows. For applied physics aspects the energy characteristics of ion fluxes attacking the electrode surface is of great interest. We have investigated experimentally the energy spectra of ions striking cathode in abnormal glow discharges for discharge current densities in the range of 10-100 mA/cm2 and gas pressure above 1 Torr in molecular (H2 and D2) and in noble gases (He and Ar). We have built up a Monte-Carlo model of the discharge and applied it to abnormal glow discharges in helium and hydrogen. The studies aimed to improve discharge facility, which used for ion implantation of first wall metal patterns in fusion devices. I took part in all parts of the studies and, especially, in analytical and numerical model development.

Wave propagation in a plane heterogeneous dielectric waveguide

My thesis work for B.Sc. was dedicated to the investigation of wave propagation in a plane heterogeneous dielectric waveguide (scientific supervisor Prof. E. Belokolos). We extended a very narrow class of the profile of dielectric permeability º(z) that allows exact analytical solutions. In addition to the known linear, parabolic and Epshtain profiles we found that profile º(z) in the form of the Weierstrass P-function allows rigorous solutions. The set of Maxwell equations was reduced to Shröedinger equation and later on was presented in the form of the Lame equation. The latter equation was analyzed for arbitrary boundary conditions and rigorous solutions have been found. At the same time we elaborated principles of the approach on the base of inverse spectral problem, which allowed determining the profiles of dielectric permeability by known (or required) spectral characteristics.

 

 Updated Monday, November 24, 2003
© Alexei Pankin