L. Grisham
Abstract
The deuterium-tritium plasmas of the TFTR tokamka will be well characterized, with all existing diagnostics being upgraded as needed. The bulk of the heating power will be provided by neutral beams. About 75% of tritium beam power will be at full beam energy. This report describes the plasma evaluation program.
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The deuterium-tritium plasmas of the TFTR tokamka will be well characterized, with all existing diagnostics being upgraded as needed. The bulk of the heating power will be provided by neutral beams. About 75% of tritium beam power will be at full beam energy. This report describes the plasma evaluation program.
Key concepts: Tritium, Tokamak, Nuclear engineering, Deuterium, Nuclear physics, Beam (structure), Tokamak Fusion Test Reactor, Plasma