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Fusion Science and Technology
NRC schedules webinars on Holtec’s proposed New Mexico storage site
The Nuclear Regulatory Commission has scheduled four webinars in late August and early September to present its draft environmental findings and receive comments on Holtec International’s proposed consolidated spent nuclear fuel storage facility in New Mexico. Webinars were previously held on June 23 and July 9.
As published in the August 13 Federal Register, the public comment webinars will be held on August 20 from 6–9 p.m., August 25 from 2–5 p.m., August 26 from 6–9 p.m., and September 2 from 11 a.m.–2 p.m. All times are Eastern. Information for the webinars is posted on the NRC’s Public Meetings webpage.
E.P. Kruglyakov, G.I. Dimov, A.A. Ivanov, V.S. Koidan
Fusion Science and Technology | Volume 43 | Number 1 | January 2003 | Pages 16-22
Overview | dx.doi.org/10.13182/FST03-A11963557
Articles are hosted by Taylor and Francis Online.
Mirrors are the only one class of fusion systems which completely differs topologically from the systems with closed magnetic configurations. At present, there modern types of different mirror machines for plasma confinement and heating exist in Novosibirsk (Gas Dynamic Trap, -GDI, Multi-mirror, -GOL-3, and Tandem Mirror, -AMBAL-M). All these systems are attractive from the engineering point of view because of very simple axisymmetric geometry of magnetic configurations. In the present paper, the status of different confinement systems is presented. The experiments most crucial for the mirror concept are described such as a demonstration of different principles of suppression of electron heat conductivity (GDT, GOL-3), finding of MHD stable regimes of plasma confinement in axisymmetric geometric of magnetic field (GDT, AMBAL-M), an effective heating of a dense plasma by relativistic electron beam (GOL-3), observation of radial diffusion of quiescent plasma with practically classical diffusion coefficient (AMBAL-M), etc.
It should be mentioned that on the basis of the GDT it is possible to make a very important intermediate step. Using “warm” plasma and oblique injection of fast atoms of D and T one can create a powerful 14 MeV neutron source with a moderate irradiation area (about 1 square meter) and, accordingly, with low tritium consumption. It should be mentioned that there is no one candidate to the plasma based neutron source with such a low (about 150 gram/year) tritium consumption.
The main plasma parameters achieved are presented.