Open ended axially symmetric systems. Results and perspectives

Significant progress of the simplest axisymmetric magnetic systems for plasma confinement and heating is described. Two of such systems are presented in this paper: multi mirror (GOL-3) and gas dynamic (GDT) traps. In the GOL-3 case the temperatures Te ≈ Е ≈ 2 keV were obtained in a dense (of or...

Full description

Saved in:
Bibliographic Details
Published in:Вопросы атомной науки и техники
Date:2006
Main Authors: Burdakov, A.V., Ivanov, A.A., Kruglyakov, E.P.
Format: Article
Language:English
Published: Національний науковий центр «Харківський фізико-технічний інститут» НАН України 2006
Subjects:
Online Access:https://nasplib.isofts.kiev.ua/handle/123456789/81772
Tags: Add Tag
No Tags, Be the first to tag this record!
Journal Title:Digital Library of Periodicals of National Academy of Sciences of Ukraine
Cite this:Open ended axially symmetric systems. Results and perspectives / A.V. Burdakov, A.A. Ivanov, E.P. Kruglyakov // Вопросы атомной науки и техники. — 2006. — № 6. — С. 29-33. — Бібліогр.: 26 назв. — англ.

Institution

Digital Library of Periodicals of National Academy of Sciences of Ukraine
Description
Summary:Significant progress of the simplest axisymmetric magnetic systems for plasma confinement and heating is described. Two of such systems are presented in this paper: multi mirror (GOL-3) and gas dynamic (GDT) traps. In the GOL-3 case the temperatures Te ≈ Е ≈ 2 keV were obtained in a dense (of order of 10²¹m⁻³) plasma and the maximum value of nIJE ≈ 2·10¹⁸m⁻³s was achieved. Any physical limitations which could prevent from further grow of plasma parameters did not find out. The most important results obtained in the experiments on GDT are described. A new step (GDT-U) has been prepared and the first preliminary experiments with quasi-stationary plasma heating have started. According to calculations, the parameters of the GDT-U should demonstrate the feasibility of “moderate” (0.5 MW/m²) 14 MeV neutron source for structural materials tests of fusion reactor.
ISSN:1562-6016