Evaluation of a nonevaporable getter pump for tritium handling in the Tokamak Fusion Test Reactor [electronic resource].

Published:: Livermore, Calif. : Lawrence Livermore Laboratory, 1978.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: Pages: 14 : digital, PDF file
Additional Creators:: Lawrence Livermore Laboratory and United States. Department of Energy. Office of Scientific and Technical Information

Access Online

www.osti.gov

Availability

Finding items...

Restrictions on Access:

Free-to-read Unrestricted online access

Summary:

Lawrence Livermore Laboratory has tested and evaluated a commercially available getter pump for use with tritium in the Tokamak Fusion Test Reactor (TFTR). The pump contains Zr(84%)--Al in cartridge form with a concentric heating unit. It performed well in all tests, except for frequent heater failures.

Report Numbers:

E 1.99:ucrl-52584
ucrl-52584

Subject(s):

Plasma Physics And Fusion Technology

Other Subject(s):

Note:

Published through SciTech Connect.
09/28/1978.
"ucrl-52584"
Griffith, C.M.; Singleton, M.F.

Funding Information:

W-7405-ENG-48

View MARC record | catkey: 14755022