Open AccessOutgassing tests on materials used in the DIII-D magnetic fusion tokamak
Author(s) -
K.L. Holtrop,
M. Hansink,
A.G. Kellman
Publication year - 1998
Language(s) - English
Resource type - Reports
DOI - 10.2172/291186
Subject(s) - outgassing , tokamak , diii d , materials science , nuclear engineering , graphite , fusion power , magnet , impurity , nuclear fusion , electromagnet , plasma , tore supra , analytical chemistry (journal) , nuclear physics , composite material , chemistry , physics , electrical engineering , engineering , chromatography , organic chemistry
In order to achieve high performance plasma discharges in the DIII-D magnetic fusion tokamak, impurity levels must be carefully controlled. Since first wall materials can desorb volatile impurities during these discharges, it is important to characterize and control the outgassing of these materials. An outgassing chamber was built to measure the outgassing properties of various materials used in the DIII-D vessel. The results of pump-down tests performed on ATJ graphite, thin Grafoil {reg_sign} gaskets, and MgO coaxial cables will be presented. In addition to pumpdown tests it was desired to study the behavior of the materials at temperatures up to 400 C, which is the maximum temperature to which the DIII-D vessel is baked. The station was modified to include independent heating control of the sample and a simple load-lock chamber