64 research outputs found
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Technology of direct conversion for mirror reactor end-loss plasma
Design concepts are presented for plasma direct convertors (PDC) intended primarily for use on the end-loss plasma from tandem-mirror reactors. Recent experimental results confirm most of these design concepts. Both a one-stage and a two-stage PDC were tested in reactor-like conditions using a 100-kV, 6-kW ion beam. In a separate test on the end of the TMX machine, a single stage PDC recovered 79 W for a net efficiency of 50%. Tandem mirror devices are well suited to PDC. The high minimum energy of the end-loss ions, the magnetic expansion outside the mirrors, and the vacuum conditions in the end tanks required by the confined plasma, all preexist. The inclusion of a PDC is therefore a rather small addition. These facts and the scale parameters for a PDC are discussed
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Mirror fusion reactor study
The principal features of a fusion power reactor employing the magnetic mirror confinement concept are described. A parametric design and cost estimate analysis has been used to optimize the design for minimum capital cost per net electric output. Optimized parameters include the vacuum mirror ratio, the injection energy and angle, the choice of a thermal conversion cycle, and the design efficiency of the charged particle direct converter. The sensitivity of the cost of power for the optimized design to variations in many of the reactor parameters is discussed. (auth
Trapped Particle Stability for the Kinetic Stabilizer
A kinetically stabilized axially symmetric tandem mirror (KSTM) uses the
momentum flux of low-energy, unconfined particles that sample only the outer
end-regions of the mirror plugs, where large favorable field-line curvature
exists. The window of operation is determined for achieving MHD stability with
tolerable energy drain from the kinetic stabilizer. Then MHD stable systems are
analyzed for stability of the trapped particle mode. This mode is characterized
by the detachment of the central-cell plasma from the kinetic stabilizer region
without inducing field-line bending. Stability of the trapped particle mode is
sensitive to the electron connection between the stabilizer and the end plug.
It is found that the stability condition for the trapped particle mode is more
constraining than the stability condition for the MHD mode, and it is
challenging to satisfy the required power constraint. Furthermore a severe
power drain may arise from the necessary connection of low-energy electrons in
the kinetic stabilizer to the central region
Comparative proteomic analyses of the nuclear envelope and pore complex suggests a wide range of heretofore unexpected functions
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Beryllium usage in fusion blankets and beryllium data needs. [None]
Increasing numbers of designers are choosing beryllium for fusion reactor blankets because it, among all nonfissile materials, produces the highest number (2.5 neutron in an infinite media) of neutrons per 14-MeV incident neutron. In amounts of about 20 cm of equivalent solid density, it can be used to produce fissile material, to breed all the tritium consumed in ITER from outboard blankets only, and in designs to produce Co-60. The problem is that predictions of neutron multiplication in beryllium are off by some 10 to 20% and appear to be on the high side, which means that better multiplication measurements and numerical methods are needed. The n,2n reactions result in two helium atoms, which cause radiation damage in the form of hardening at low temperatures (<300/degree/C) and swelling at high temperatures (>300/degree/C). The usual way beryllium parts are made is by hot pressing the powder. A lower cost method is to cold press and then sinter. There is no radiation damage data on this form of beryllium. The issues of corrosion, safety relative to the release of the tritium built-up inside beryllium, and recycle of used beryllium are also discussed. 10 figs
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Review of direct energy conversion of ion beams: experimental results and reactor applications
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Hybrid reactors. [Fuel cycle]
The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of /sup 233/U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m/sup -2/, and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid
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Conceptual design considerations for D-T mirror reactors with and without a fission blanket
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Physics of mirror reactors and devices
BS>From surface effects in controlled thermonuclear fusion devices and reactors Meeting; Argonne, Illinois, USA (10 Jan 1974). The physics of plasma confinement using the magnetic mirror principle is discussed, and the unique features of the mirror reactor approach to fusion are discussed and compared to the toroidal confinement approach. (auth
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Technology requirements for fusion--fission reactors based on magnetic-mirror confinement
Technology requirements for mirror hybrid reactors are discussed. The required 120-keV neutral beams can use positive ions. The magnetic fields are 8 T or under and can use NbTi superconductors. The value of Q (where Q is the ratio of fusion power to injection power) should be in the range of 1 to 2 for economic reasons relating to the cost of recirculating power. The wall loading of 14-MeV neutrons should be in the range of 1 to 2 MW/m/sup 2/ for economic reasons. Five-times higher wall loading will likely be needed if fusion reactors are to be economical. The magnetic mirror experiments 2XIIB, TMX, and MFTF are described
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