Plasma assessments for the Fusion Engineering Device (FED)

An initial range of plasma assumptions and scenarios was examined for the US Tokamak fusion engineering device (FED) concept. The results suggest that the current FED baseline parameters of R = 4.8 m, B/sub t/ = 3.6 T, a = 1.3 m, b = 2.1 m (D-shape), and I/sub p/ = 4.8 to 5.4 MA are appropriate for achieving its nominal goals of P(fusion) approx. = 180 MW and a plasma Q greater than or equal to 5 a pulse length greater than 100 s. However, large uncertainty still exists in the areas of current startup, ion cyclotron wave launching, influence of plasma shape on achievable beta, in purity control, plasma edge transport, and plasma disruption. Various options and remedies, suggested to alleviate the impact of the uncertainty on the FED design concept, appear promising because they can be studied experimentally and are not expected to lead to fundamental design modifications of FED.