COMPX SM
Computational Modeling and Software Development

 

CQL3D Code

Description | Purpose | Algorithms | Results | Publications | Documentation

Short Description

The relativistic Collisional/QuasiLinear 3D code CQL3D solves a Bounce-Averaged Fokker-Planck equation to obtain the 3 1/2-D distributions of electrons and multispecies ions, resulting from the balance between collisions, RF/neutral beam sources and applied toroidal electric field, in toroidal geometry. (3 1/2-D refers to 2 velocity, 1 radius, and implicit treatment of the poloidal variation through the bounce-averaging.) Steady-state and time-dependent solutions are supported.

Dates/Active Use

1985 to present

Authors

R.W. Harvey and M.G. McCoy

Language

Fortran

Purpose/Function/Special Features

The overall aim for CQL3D is to create a general facility for the accurate calculation of heating and current drive in tokamaks. To the extent possible, all the physics effects which are known to be important in such calculations should be included. CQL3d is a multi-species, 2D-in-momentum-space, 1D in noncircular plasma radial cooordinate, fully relativistic, bounce-averaged, collisional/quasilinear Fokker-Planck equation solver. It is run in combination with LH, FW, EC and EBW ray tracing or full-wave (AORSA) rf data, the FREYA neutral beam deposition package, and a given toroidal electric field, thereby providing a general model for the distortion of the electron and ion distribution functions resulting from auxiliary heating and current drive injected from the plasma periphery. The distributions are taken to be toroidally symmetric and independent of azimuthal angle about the ambient magnetic field. Radial drifts are neglected. With the bounce-average, account is taken of variations as a function of (non-circular) radial coordinate, poloidal angle, and two momentum-space directions. A kinetic bootstrap current calculation is included. The code may be run with separate 2D momentum space solves on each flux surface, on in 3D mode including radial transport according to prescribed diffusion and pinch terms.

Although the focus of the code has been on electrons, it is a multispecies code, i.e., it can treat electron and multiple ion distributions simultaneously. The NFREYA neutral beam deposition module is coupled in for modeling of neutral beam current drive.

Basic Algorithms

The steady state distributions and the radial rf absorption profile are obtained by iteration between (1) the Guassian elimination solution of the Fokker-Planck equation for the steady state on each flux surface, and (2) the rf energy transport equation integrated along a ray.

The computational scheme for time advancement consists of an alternating direction implicit scheme, between the two momentum-space variables and the radial variable. The momentum-space equation is solved in a fully implicit, direct gaussian elimination scheme previously developed for the 2D in momentum-space CQL code. Similarly, the radial variable is advanced fully implicitly, presently by a splitting algorithm alternating with the velocity-space advancement. Work in progress on a fully-implicit solution of the 3D (2V,1R) equations[April/04].

Coupled Diagnostics

The distribution functions from CQL3D are coupled to calculations of:
  • X-ray Bremsstrahlung energy spectra along specified sight-lines.
  • Electron cyclotron [and EBW] microwave emission, solving the plasma wave energy transport equation along rays terminating at a detector [with GENRAY]. Emission and absorption is based upon general 2D velocity distributions.
  • NPA charge exchange spectra [work with Rosenberg/Andre, PPPL].

Key Results

CQL3D results have strongly influenced the course of several important rf current drive experiments and proposals, specifically (1) experiments at GA and collaboration with Kurchatov Institute, Moscow[3], (2) implementation and interpretation of the lower hybrid current profile control experiments on the ASDEX experiment[4] and the associated planning for the PBX lower hybrid current profile control- MHD second stability region-experiment[5], (3) interpretation of fast wave current drive (FWCD) and ECCD experiments at GA[6,7], and (4) consideration of FWCD synergy with electron cyclotron resonance heating (ECRH)[8], and electron cycltron CD [9] in tokamak reactor environments.

An ECCD result first obtained unambiguously by CQL3D([10]), is that current drive by outside (i.e., outboard side) launch of the rf power is strongly preferred to inside launch, based on current drive efficiency. For inside launch, ECCD efficiency at low power is about one-half of that for the outside launch; as rf power increased, the inside launch efficiency can decrease and even pass through zero. In addition, outside launch efficiency doubles at high rf power. As a result of CQL3D, a new outside launch configuration was implemented in DIII-D.

CQL3D current drive results have since been shown to agree in detail with DIII-D experimental data near both the first and second cylcotron harmonics.[6,7].

The code has provided detailed estimates of EC current drive in ITER, contributing strongly to the advancment of this scheme for current profile control [9].

Application of the code has been made to several additional tokamak experiments: FT-1 (Joffe), Tore Supra, T-10, TdeV, Versator-II. The code has lead in devolpment of similar codes in Europe and Japan[11].

New applications are being made to the disruption/runaway electron problem.

Radial transport modeling proved to be a decisive factor in interpretation of the TCV ECCD experiment [12] and the MST reversed field pinch[13].

Selected Publications

  1. R.W. Harvey and M.G. McCoy, The CQL3D Code, Proc. IAEA TCM on Advances in Sim. and Modeling of Thermonuclear Plasmas, Montreal, (1992) p. 527, available through USDOC/NTIS No. DE93002962.
  2. G.D. Kerbel and M.G. McCoy, Phys. Fl. No. 28, p. 3629 (1985).
  3. V.V. Alikaev et al, Electron Cyclotron Current Drive Experiment on T-10, Nucl. Fus. 32 p. 1811(1992), and 35 p.369 (1995).
  4. F.X. Soeldner et al., Review of Lower Hybrid Experiments on Asdex, in Plasma Physics and Controlled Thermonuclear Fusion Research (Proc. 13th Int. Conf. Washington, 1990) (IAEA, Vienna, 1991) Vol.I, p.613.
  5. S. Bernabei, personal communication (1993).
  6. C.C.Petty, et al., Fast Wave and Electron Cyclotron Current Drive in the DIII-D Tokamak, Nucl. Fus., Vol. 35, p. 773 (1995).
  7. R.A.James, C.C.Petty, and R.W.Harvey, A Comparison of Fundamental and Second Harmonic Inside Launch ECCD in the Presence of a DC Electric Field, Proc. of EC-9 Workshop on Electron Cyclotron Emission and Electron Cyclotron Heating Conference, Borrego Springs, CA (1995).
  8. R.W. Harvey, et al., Calculation of Combined Fast Wave/Lower Hybrid and Electron Cyclotron Current Drive in Tokamaks, in Proceedings of IAEA TCM on Fast Wave Current Drive in Reactor Scale Tokamaks (Synergy and Complementarity with LHCD and ECRH), Arles, France, 1991 (IAEA, Vienna).
  9. Electron Cyclotron Heating and Current Drive in ITER, R.W.Harvey, W.M.Nevins, G.R.Smith, B.Lloyd, M.R.O'Brien, and C.D.Warrick, GA Report GA-A22141 (Submitted to Nucl. Fus., 1996)
  10. R.W. Harvey, M.G. McCoy, and G.D. Kerbel, Power Dependence of Electron-Cyclotron Current Drive for Low- and High-Field Absorption in Tokamaks, PRL,62 (1989) 426.
  11. E. Westerhof, Fokker-Planck Quasi-Linear Codes for the Study of Electron Cyclotron Resonance Heating and Electron Cyclotron Current Drive, in Proc. of 9th Joint Workshop on ECE and ECRH, Borrego Springs, 1995.
  12. R.W. Harvey, O. Sauter, R. Prater, and P. Nikkola, Radial transport and electron cyclotron current drive in the TCV and DIII-D tokamaks, Phys. Rev. Lett. {\bf 88}, Article 205001 (May, 2002).
  13. R. O'Connell, D.J. Hartog, C.B. Forest, J.K. Anderson, S.C. Prager, J.S. Sarff, T.M. Biewer, S.D. Terry, R.W. Harvey, Transition from stochastic magnetic to electrostatic-like transport in the Reversed Field Pinch, Phys. Rev. Lett. 91, 045002 (2003).

Documentation

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