Engineering design of a fusion test reactor (FTB) and fusion engineering research facility (FERF) based on a toroidal theta pinch
This paper describes two advanced toroidal theta-pinch devices which are being proposed for future construction. The Fusion Test Reactor (FTR) is being designed to produce thermonuclear energy (at 20 MeV/neutron) equal to the maximum plasma energy (Q = 1) and to demonstrate $alpha$-particle heating. The Fusion Engineering and Research Facility (FERF) is being designed to test materials in a fusion environment where the average 14-MeV neutron flux from the plasma is greater than or equal to 5 x 10$sup 13$ n/cm$sup 2$.s over large surface areas. These devices employ the staged theta-pinch principle where the heating is accomplished by rapid (approximately 0.1 $mu$s) implosion and expansion followed by a slow compression of the plasma. The rapid implosion injects as much heat as possible at as large a plasma radius as possible so that the plasma remains stable even after further compression. The final compression to ignition requires the transfer of a large amount of magnetic energy which implies a long transfer time (approximately 1 ms) for realistic voltages in the driving circuit. Throughout the heating and burn cycle the plasma must remain in equilibrium and stable to the dominant MHD-modes. A sufficiently large plasma radius guarantees stability against the m = 1 modes. These equilibrium and stability conditions and the requirements on thermonuclear burn determine the design parameters for either machine. The design parameters must also be consistent with economic limitations and technological feasibility of components. In addition to these requirements, the FERF must provide a steady and reliable source of fusion neutrons. (auth)
- Research Organization:
- Argonne National Lab., IL
- NSA Number:
- NSA-33-014582
- OSTI ID:
- 4093291
- Resource Relation:
- Conference: 5. conference on plasma physics and controlled nuclear fusion research, Tokyo, Japan, 11 Nov 1974; Other Information: See STI/PUB--381(Vol.3); CONF-741105--P3. Orig. Receipt Date: 30-JUN-76; Related Information: Plasma physics and controlled nuclear fusion research, 1974. Vol. III
- Country of Publication:
- IAEA
- Language:
- English
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