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Title: ISX: a tokamak for surface and impurities studies

Conference ·
OSTI ID:4067641

The ISX (Impurity Study Experiment) is a moderate size tokamak slightly larger than the ORMAK tokamak. ISX is being built explicitly for the study of impurities and plasma-wall interactions. It is scheduled to begin experiments in the spring of 1977. Several features have been deliberately designed into the ISX which make it particularly adaptable to surface studies. The first is a welded stainless steel vacuum system, bakeable to 400$sup 0$C, with a projected base pressure greater than or equal to 2 x 10$sup -9$ torr. Another feature is that of ''easy'' demountability of the vacuum system. Replacement of the entire vacuum system should take about two weeks. A third feature is diagnostic access to the edges of the plasma. The initial surface physics question to be answered is how best to keep surfaces clean: by baking, by direct or indirect wall bombardment discharges, or by gettering. Later experiments will involve using wall materials other than stainless steel to determine their effects on the plasma. (auth)

Research Organization:
Oak Ridge National Lab., Tenn. (USA)
NSA Number:
NSA-33-022985
OSTI ID:
4067641
Report Number(s):
CONF-760209-7
Resource Relation:
Conference: 2. international conference on surface effects in controlled fusion devices, San Francisco, California, United States of America (USA), 16 Feb 1976; Other Information: Orig. Receipt Date: 30-JUN-76
Country of Publication:
United States
Language:
English