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Abstract

More consistent numerical simulation of divertor tokamak edges relies on iteration of plasma and Monte Carlo neutral particle transport models in a common realistic geometry. Using existing HF magnetostatic equilibrium data, a new linear interpolation program denoted LINDA provides spatial discretisations everywhere closely aligned with axisymmetric magnetic structure. For a single-null poloidal divertor, chosen arrangements of piecewise linear magnetic flux surfaces are constructed, and deriving from a novel isosceles technique also orthogonal surfaces. Resulting grids are described explicitly in poloidal plane co-ordinates for neutral particle codes, and in fundamental metric functions detailing cell orthogonal diameters, interfacial areas and volumes for the BRAAMS steady-state plasma code. By imposing constant total and poloidal flux tube constraints and approximating connection length integrals, consistent specifications are determined simultaneously for both along magnetic field and poloidal cross-section co-ordinate versions. Example output for case NET-3A is presented. Expediting BRAAMS applications by evolving magnetic shear and extension to double-null configurations are considered.

Additional information

Authors: MADDISON G P CULHAM LABORATORY, ABINGDON (UK), CULHAM LABORATORY, ABINGDON (UK)
Bibliographic Reference: WRITE TO THE LIBRARIAN, UKAEA, CULHAM LABORATORY, ABINGDON, OXON OX14 3DB (UK), MENTIONING REPORT CLM-P825, 1987
Record Number: 1989126057800 / Last updated on: 1989-03-01
Category: PUBLICATION
Available languages: en