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Title: Summary of results from the TEXTOR helium self-pumping experiment

Conference ·
OSTI ID:10150139
;  [1]; ;  [2]; ;  [3]
  1. Argonne National Lab., IL (United States)
  2. Sandia National Labs., Albuquerque, NM (United States)
  3. Association Euratom-Kernforschungsanlage Juelich (Germany). Inst. fuer Plasmaphysik

Helium removal experiments were conducted in TEXTOR with a small helium self-pumping module located in a modified ALT-I limiter head. The module contained two heated nickel alloy trapping plates, a nickel deposition filament array, a Langmuir probe, flux probe, and thermocouples. The experiment examined plasma helium removal via trapping of helium ions in the deposited nickel surfaces. Such helium removal was successfully observed, with about 10% of the helium He/D plasma being removed in a {approximately}1 s period. The module was found to be compatible with overall tokamak operation with essentially no sputtered nickel entering the core plasma. The temperature rise on the ion-exposed inner trapping plate, during a plasma shot, is consistent with a nickel a local sheath potential of {approximately}3 kT{sub e}. Post-tokamak test examination of the trapping plates shows helium atom concentrations in the deposited nickel consistent with the observed helium removal, and shows very small D concentrations.

Research Organization:
Argonne National Lab., IL (United States)
Sponsoring Organization:
USDOE, Washington, DC (United States)
DOE Contract Number:
W-31109-ENG-38; AC04-76DP00789
OSTI ID:
10150139
Report Number(s):
ANL/CP-74780; SAND-92-1266C; CONF-920311-15; ON: DE92015185; TRN: 92:021822
Resource Relation:
Other Information: PBD: Mar 1992
Country of Publication:
United States
Language:
English