Tritium experience in the Tokamak Fusion Test Reactor [electronic resource].
- Washington, D.C. : United States. Dept. of Energy. Office of Energy Research, 1998.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
- Physical Description:
- 4 pages : digital, PDF file
- Additional Creators:
- Princeton University
United States. Department of Energy. Office of Energy Research
United States. Department of Energy. Office of Scientific and Technical Information
- Tritium management is a key enabling element in fusion technology. Tritium fuel was used in 3.5 years of successful deuterium-tritium (D-T) operations in the Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory. The D-T campaign enabled TFTR to explore the transport, alpha physics, and MHD stability of a reactor core. It also provided experience with tritium retention and removal that highlighted the importance of these issues in future D-T machines. In this paper, the authors summarize the tritium retention and removal experience in TFTR and its implications for future reactors.
- Published through SciTech Connect.
20. symposium on fusion technology (SOFT `98), Marseille (France), 7-11 Sep 1998.
Brooks, J.N.; Blanchard, W.; Mueller, D.; Hogan, J.; Skinner, C.H.; Hosea, J.; Nagy, A.
- Funding Information:
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