Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1569238 | Journal of Nuclear Materials | 2007 | 6 Pages |
Abstract
HT-7 is a medium-sized superconducting tokamak with limiter and circular cross section configuration and it has become an important target for modelling of experimental plasmas. SOLPS5.0(B2.5) edge plasma transport code is used for modelling the experimental shots in order to match the code results to the experimental temperature and density profiles by varying the perpendicular particle transport coefficient D and heat conductivities Ïe, Ïi in the code until good agreement between the code results and the measured data. For ohmic heated Deuterium plasma shot with toroidal magnetic field Bt = 1.98 T, plasma current Ip = 140 kA, ohmic heating power P = 180 kW, by matching the modelling results to the experimental profiles of electron density and temperature at the orthogonal plane, the perpendicular particle and heat transport coefficients D, Ïe and Ïi are obtained from the modelling results in the edge computation region with the assumption of Ïe = Ïi.
Keywords
Related Topics
Physical Sciences and Engineering
Energy
Nuclear Energy and Engineering
Authors
YiPing Chen, Guosheng Xu, Jiansheng Hu, D.P. Coster,