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Neutral Gas Transport Calculations for ITER
Author(s) -
Grossman A.,
Schmitz L.,
Merriman B.,
Najmabadi F.
Publication year - 1996
Publication title -
contributions to plasma physics
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.531
H-Index - 47
eISSN - 1521-3986
pISSN - 0863-1042
DOI - 10.1002/ctpp.2150360246
Subject(s) - divertor , tokamak , plasma , enhanced data rates for gsm evolution , materials science , geometry , magnetic field , nuclear engineering , computational physics , physics , computer science , nuclear physics , telecommunications , mathematics , quantum mechanics , engineering
In modeling the neutral transport in the edge plasma for tokamak divertor design, geometry can play as important a role as the plasma density and temperature profiles. We have developed a novel interface between the neutral transport code, DEGAS, and CAD images of the tokamak and magnetic field geometry, which provides an accurate representation of the wall geometry for neutral transport modelling. In addition to superior spatial resolution of the vessel geometry, the interface allows subset regions of special interest to be selected out for modeling and permits the wall geometry to be readily modified by point and click techniques. Neutral transport results for the two divertor geometries under consideration for ITER, the gas bag design and the v‐shaped target design, are presented.