Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

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
Country of Publication:
United States
Language:
English

Similar Records

Surface impurity studies in the ISX-A tokamak
Journal Article · Wed Feb 28 23:00:00 EST 1979 · J. Vac. Sci. Technol.; (United States) · OSTI ID:6348597

Surface impurity studies in the ISX-A tokamak
Conference · Sat Dec 31 23:00:00 EST 1977 · OSTI ID:6448636

Plasma confinement and impurity flow reversal experiments in the ISX-A Tokamak
Conference · Sat Dec 31 23:00:00 EST 1977 · OSTI ID:6532566