Author
A. R. Polevoy
Bio: A. R. Polevoy is an academic researcher from Kurchatov Institute. The author has contributed to research in topics: Tokamak & Divertor. The author has an hindex of 2, co-authored 3 publications receiving 9 citations.
Topics: Tokamak, Divertor, Spherical tokamak, Neutron source, Solenoid
Papers
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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
TL;DR: The Joint Upgraded Spherical Tokamak (JUST) as mentioned in this paper is a multifunctional facility for working out of physical regimes (discharge scenarios, mode of buming, limits of working plasma parameters), promising divertor devices and testing of reactor materials.
Abstract: Concept of the Joint Upgraded Spherical Tokamak (JUST) – a multifunctional facility for working out of physical regimes (discharge scenarios, mode of buming, limits of working plasma parameters), promising divertor devices and testing of reactor materials is presented. The proposed JUST parameters are: R = 1.8 m; a = 1.2 m; A = 1.5; k = 2.3; Bto = 2.1 T; Ip = 10-14 MA, P AUX = 15-20 MW; P FUS∼ 50 MW, tburn ∼ 10 s. Results of the preliminary study of the tokamak design are presented. Wide use of Russian industrial experience in creation of super-powerful electro-generators and advanced technologies of airspace complexes is planned.
2 citations
01 Jan 1997
TL;DR: In this paper, the authors present a brief description of the stages of the joint upgrated spherical tokamak (JUST) project, including the electromagnetic system, the toroidal field coils, and the poloidal system coils.
Abstract: Publisher Summary The development of spherical tokamak project, joint upgrated spherical tokamak (JUST), has come through several stages. Each of the stages allows defining key points of the project, leading to the changes of the parameters. This chapter presents a brief description of these stages. The electromagnetic system is the most complex system of JUST device, which is a central core consisting of an ohmic heating solenoid and a toroidal field coil and is subjected to high level electromagnetic and thermal stresses. The ohmic heating solenoid consists of two coaxial coils divided to cylindrical insulating layer. From all poloidal system coils, the coils of group PF-2 are the most difficult to realize because they are located in the limited space near central core and have maximum current — 6MA — turns.
1 citations
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TL;DR: In this paper, a compact volumetric neutron source on the spherical tokamak is proposed for minor actinides transmutation with aspect ratio A'n'='2', where the plasma current is initiated inductively and then bootstrap current will generate with using additional heating by injection of neutral beams.
Abstract: By concept development of the compact volumetric neutron source on the spherical tokamak JUST basis for minor actinides transmutation with aspect ratio A = 2, some key plasma physics problems are arising: start of discharge; plasma current maintenance in stationary stage; appropriate neutron fluence for transmutation. On the basis of accepted physical and technical preconditions of the concept the combined scenario of current start and ramp-up, its stationary maintenance due to bootstrap effect and drive by neutral particle injection are considered. The plasma current is proposed to be initiated inductively and then bootstrap current will generate with using additional heating by injection of neutral beams. Necessary neutron flux for effective transmutation (Γn ≈ 0.4 MW/m2) will be reached by both plasma-beam reactions and thermal plasma fusion reactions. By the way of preliminary consideration engineering studies of vacuum chamber, toroidal magnetic system, divertor, and blanket with energy multiplicatio...
18 citations
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
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
TL;DR: Problems of the plasma scenario realization in a volumetric neutron source of the tokamak type are discussed in this article, namely the generation of the forecurrent followed by the non-inductive pl...
Abstract: Problems of the plasma scenario realization in a volumetric neutron source of the tokamak type are discussed in the paper, namely the generation of the fore-current followed by the non-inductive pl...
2 citations
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.