The TEXTOR helium self-pumping experiment: Design, plans, and supporting ion-beam data on helium retention in nickel

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6860671

Brooks, J N; Krauss, A; Mattas, R F; Smith, D L ^[1]; Nygren, R E; Doyle, B L; McGrath, R T; Walsh, D ^[2]; Dippel, K H

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1. Argonne National Lab., IL (USA)
2. Sandia National Labs., Albuquerque, NM (USA)

A proof-of-principle experiment to demonstrate helium self-pumping in a tokamak is being undertaken in TEXTOR. The experiment will use a helium self-pumping module installed in a modified ALT-I limiter head. The module consists of two, {approximately}25 {times} 25 cm{sup 2} heated nickel alloy trapping plates, a nickel deposition filament array, and associated diagnostics. Between plasma shots a coating of {approximately}50 {angstrom} nickel will be deposited on the two trapping plates. During a shot helium and hydrogen ions will impinge on the plates through a {approximately}3 cm wide entrance slot. The helium removal capability, due to trapping in the nickel, will be assessed for a variety of plasma conditions. In support of the tokamak experiment, the trapping of helium over a range of ion fluences and surface temperatures, and detrapping during subsequent exposure to hydrogen, were measured in ion beam experiments using evaporated nickel surfaces similar to that expected in TEXTOR. Also, the retention of H and He after exposure of a nickel surface to mixed He/H plasmas has bee measured. The results appear favorable, showing high helium trapping ({approximately}10--50% He/Ni) and little or no detrapping by hydrogen. The TEXTOR experiment is planned to begin in 1991. 12 refs., 2 figs., 2 tabs.

• Research Organization: Sandia National Labs., Albuquerque, NM (USA)
• Sponsoring Organization: DOE/ER
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6860671
• Report Number(s): CONF-900505-7; ON: DE90013678; TRN: 90-022122
• Resource Relation: Conference: 9. plasma surface interactions in controlled fusion devices conference, Bournemouth (UK), 20-25 May 1990
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
HELIUM
TRAPPING
IMPURITIES
PUMPING
SELF-PUMPING SYSTEMS
DESIGN
ION BEAMS
NICKEL
TEXTOR TOKAMAK
BEAMS
CIRCULATING SYSTEMS
CLOSED PLASMA DEVICES
ELEMENTS
FLUIDS
GASES
METALS
NONMETALS
RARE GASES
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
TRANSITION ELEMENTS
700201* - Fusion Power Plant Technology- Blanket Engineering