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A.N. Makhankov

Bio: A.N. Makhankov is an academic researcher. The author has contributed to research in topics: Tokamak & Neutron source. The author has an hindex of 1, co-authored 1 publications receiving 6 citations.

Papers
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Journal ArticleDOI
TL;DR: In this paper, the problems of volumetric neutron source (VNS) creation on a tokamak base with moderate to high aspect ratio ( A = 3-4.5 ) and a multiturn normal conducting (‘warm’) toroidal field magnet system are discussed.

6 citations


Cited by
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Journal ArticleDOI
TL;DR: In this article, the center post (CP) of the toroidal field coil of a spherical-torus-type facility was analyzed with respect to the normal conducting magnet system of this facility, which is characterized by harsh operation conditions.

4 citations

Journal ArticleDOI
TL;DR: In this paper, a volumetric neutron source for testing large-scale blanket components, based on a steady-state tokamak device with superconducting coils, was designed.

2 citations

Proceedings ArticleDOI
06 Oct 1997
TL;DR: In this article, a volumetric neutron source (VNS) based on tokamak foresees its high availability, therefore the most simple and reliable technical solutions are required for design of the facility, its systems and units.
Abstract: A concept of volumetric neutron source (VNS) based on tokamak foresees its high availability, therefore the most simple and reliable technical solutions are required for design of the facility, its systems and units. An electromagnet system with "warm" multiturn coils satisfies these requirements. In this case the power consumption decrease for such systems is one of the main purposes of design development. The VNS magnet system design is associated in many respects with the maximum level of coil material irradiation, which depends on inner radiation shield thickness. The ceramic electric insulation is required for the coils if the shield thickness is less than 0.2 m. The VNS toroidal field system is operated in steady-state mode under high thermal and electromagnetic loads. The coil mechanical stresses obtained is 200-300 MPa, and maximum coil turn temperature is 90-120/spl deg/C. The copper alloy of Cu-Cr-Zr type is used as a coil conductor material. The general tokamak arrangement and the requirements of simple VNS demountability need electric joints in the toroidal field coil design.
01 Jan 1989
TL;DR: An operational beta limit of 3.5 I/aB has been encountered in neutral beam heated H-mode divertor discharges in DIII-D, scaling linearly with I/aaB over a factor of 3 in I/b and beta as mentioned in this paper.
Abstract: An operational beta limit of ..beta.. less than or equal to 3.5 I/aB has been encountered in neutral beam heated H-mode divertor discharges in DIII-D, scaling linearly with I/aB over a factor of 3 in I/aB and beta. Carefully prepared discharges have run stably very close to this limit, with ..beta.. greater than or equal to 3 I/aB having been sustained for more than 1 second. The maximum beta in such discharges is limited by hard disruptions which are attributed to the ideal 2/1 kink mode. Before reaching this limit, most discharges experience a saturation or slow collapse of beta associated with low-n MHD instabilities which are consistent with stability calculations for resistive pressure-driven modes. As beta increases, MHD instabilities appear in part or all of a sequence having mode numbers m/n = 5/4, 4/3, 3/2, and 2/1. The n = 2 mode is associated with a moderate degradation of confinement, while the n = 1 mode causes a complete loss of plasma energy and disruption of the discharge. The observed beta limit is well below the maximum beta allowed by ideal high-n ballooning modes for optimized profiles, but the pressure gradient at the center and edge of the discharge more » is calculated to be near the marginally stable value, and ballooning modes may influence the pressure profile in these regions. The maximum beta reached to date, 6.8%, occurred in a discharge which was well away from both predicted and operational beta limits and ran stably with ..beta.. > 6% for 800 msec. 16 refs., 6 figs. « less
Journal ArticleDOI
TL;DR: In this article, a water-cooled and austenitic stainless-steel-structured breeding blanket system was designed for a volumetric neutron source (VNS), based on a steady-state tokamak device.