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Title: Tokamak-FED plasma-engineering assessments

Conference ·
OSTI ID:6694424

A wide range of plasma assumptions and scenarios has been examined for the current US tokamak FED concept, which aims to provide a controlled, long pulse (approx. 100 s) burning plasma with an energy amplification of greater than or equal to 5, a fusion power of 180 MW, and a neutron wall load of greater than or equal to 0.4 MW/m/sup 2/. The results of the assessment suggest that the current FED baseline parameters of R = 5.0 m, B/sub t/ = 3.6 T, a = 1.3 m, b = 2.1 m (D-shape), and I/sub p/ = 5.4 MA are appropriate in reaching the above plasma performance, despite uncertainties in several plasma physics areas, such as confinement scaling, achievable beta, impurity control, etc. To enhance the probability of achieving fusion ignition and to provide some margin against a short fall in our physics projections in FED, a limited operating capability at B/sub t/ = 4.6 T and I/sub p/ = 6.5 MA is incorporated. Various other options and remedies have also been assessed aiming to alleviate the impact of the uncertainties on the FED design concept. These approaches appear promising because they can be studied within the current fusion physics program and may lead to drastically more cost-effective FED concepts.

Research Organization:
Oak Ridge National Lab., TN (USA); Princeton Univ., NJ (USA). Plasma Physics Lab.; Michigan Univ., Ann Arbor (USA); General Atomic Co., San Diego, CA (USA)
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
6694424
Report Number(s):
CONF-811040-188; ON: DE83001883; TRN: 82-026744
Resource Relation:
Conference: 9. symposium on engineering problems of fusion research, Chicago, IL, USA, 26 Oct 1981; Other Information: Portions of document are illegible
Country of Publication:
United States
Language:
English