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Small steady-state tokamaks for testing divertors and fusion nuclear technologies are considered. Based on present physics and technology data and extrapolation to reduced R0/a, H-D-fueled tokamaks with R0 approximately 0.6-0.75 m, R0/a approximately 1.8-2.5, and B(t0) approximately 1.4-2.2 T can be driven with P(tot) approximately 4.5 MW to maintain I(p) approximately 0.5 MA and produce the ITER-level plasma edge and divertor conditions. Given an adequate steady-state divertor solution and Q approximately 1 operation based on fusion through the suprathermal component, D-T-fueled tokamaks with R0 approximately 0.8 m, R0/a approximately 2, and B(t0) approximately 4 T can be driven with P(tot) approximately 15 MW to maintain I(p) approximately 4.6 MA and produce a peak neutron wall load W(L) approximately 1 MW/m2. Such devices appear possible if the plasma properties at the lower R0/a remain tokamak-like and, for the D-T case, an unshielded center core is feasible. The use of a single conductor as the inboard leg of the toroidal field coils for this purpose is discussed. The physics issues and the design features are identified for such tokamaks with a testing duty factor goal of 10-20%.
The scoping study presented describes a relatively small tokamak reactor called the Tokamak Engineering Technology Facility (TETF). The primary objective of the TETF is to demonstrate fusion technologies required for the experimental power reactor, but it will also serve as an engineering and radiation test facility.
Plasma Science and Engineering transforms fundamental scientific research into powerful societal applications, from materials processing and healthcare to forecasting space weather. Plasma Science: Enabling Technology, Sustainability, Security and Exploration discusses the importance of plasma research, identifies important grand challenges for the next decade, and makes recommendations on funding and workforce. This publication will help federal agencies, policymakers, and academic leadership understand the importance of plasma research and make informed decisions about plasma science funding, workforce, and research directions.
The tokamak is the principal tool in controlled fusion research. This book acts as an introduction to the subject and a basic reference for theory, definitions, equations, and experimental results. The fourth edition has been completely revised, describing their development of tokamaks to the point of producing significant fusion power.
Magnetic Fusion Technology describes the technologies that are required for successful development of nuclear fusion power plants using strong magnetic fields. These technologies include: • magnet systems, • plasma heating systems, • control systems, • energy conversion systems, • advanced materials development, • vacuum systems, • cryogenic systems, • plasma diagnostics, • safety systems, and • power plant design studies. Magnetic Fusion Technology will be useful to students and to specialists working in energy research.