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Colchin, R.J.; Bush, C.E.; Edmonds, P.H.
Oak Ridge National Lab., TN (USA)1978
Oak Ridge National Lab., TN (USA)1978
AbstractAbstract
[en] The ISX-A was a tokamak designed for studying plasma-wall interactions and plasma impurities. It fulfilled this role quite well, producing reliable and reproducible plasmas which had currents up to 175 kA and energy containment times up to 30 msec. With discharge precleaning, Z/sub eff/ was as low as 1.6; with titanium evaporation, Z/sub eff/ approached 1.0. Values of Z/sub eff/ greater than or equal to 2.0 were found to be proportional to residual impurity gases in the vacuum system immediately following a discharge. However, there was no clear dependence of Z/sub eff/ on base pressure. Stainless steel limiters were used in most of the ISX-A experiments. When carbon limiters were introduced into the vacuum system, Z/sub eff/ increased to 5.6. After twelve days of cleanup with tokamak discharges, during which time Z/sub eff/ steadily decreased, the carbon limiters tended to give slightly higher values of Z/sub eff/ than stainless steel limiters. Injection of less than 1016 atoms of tungsten into discharges caused the power incident on the wall to double and the electron temperature profile to become hollow
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Aug 1978; 21 p; Available from NTIS., PC A02/MF A01
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