Tokamak DEMO-FNS: Concept of magnet system and vacuum chamber

Journal Article · Thu Dec 15 00:00:00 EST 2016 · Physics of Atomic Nuclei

DOI:https://doi.org/10.1134/S1063778816070036· OSTI ID:22612576

Ananyev, S. S. ^[1]; Belyakov, V. A.; Bondarchuk, E. N.; Voronova, A. A. ^[2]; Golikov, A. A. ^[1]; Goncharov, P. R. ^[3]; Dnestrovskij, A. Yu. ^[1]; Zapretilina, E. R. ^[2]; Ivanov, D. P. ^[1]; Kavin, A. A.; Kedrov, I. V. ^[2]; Klischenko, A. V.; Kolbasov, B. N. ^[1]; Krasnov, S. V. ^[2]; Krylov, A. I. ^[1]; Krylov, V. A.; Kuzmin, E. G. ^[2]; Kuteev, B. V. ^[1]; Labusov, A. N. ^[2]; others, and

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1. National Research Center Kurchatov Institute (Russian Federation)
2. D.V. Efremov Scientific Research Institute of Electrophysical Apparatus (Russian Federation)
3. Peter the Great St. Petersburg Polytechnic University (Russian Federation)

The level of knowledge accumulated to date in the physics and technologies of controlled thermonuclear fusion (CTF) makes it possible to begin designing fusion—fission hybrid systems that would involve a fusion neutron source (FNS) and which would admit employment for the production of fissile materials and for the transmutation of spent nuclear fuel. Modern Russian strategies for CTF development plan the construction to 2023 of tokamak-based demonstration hybrid FNS for implementing steady-state plasma burning, testing hybrid blankets, and evolving nuclear technologies. Work on designing the DEMO-FNS facility is still in its infancy. The Efremov Institute began designing its magnet system and vacuum chamber, while the Kurchatov Institute developed plasma-physics design aspects and determined basic parameters of the facility. The major radius of the plasma in the DEMO-FNS facility is R = 2.75 m, while its minor radius is a = 1 m; the plasma elongation is k{sub 95} = 2. The fusion power is P{sub FUS} = 40 MW. The toroidal magnetic field on the plasma-filament axis is B{sub t0} = 5 T. The plasma current is I{sub p} = 5 MA. The application of superconductors in the magnet system permits drastically reducing the power consumed by its magnets but requires arranging a thick radiation shield between the plasma and magnet system. The central solenoid, toroidal-field coils, and poloidal-field coils are manufactured from, respectively, Nb{sub 3}Sn, NbTi and Nb{sub 3}Sn, and NbTi. The vacuum chamber is a double-wall vessel. The space between the walls manufactured from 316L austenitic steel is filled with an iron—water radiation shield (70% of stainless steel and 30% of water).

• OSTI ID: 22612576
• Journal Information: Physics of Atomic Nuclei, Vol. 79, Issue 7; Other Information: Copyright (c) 2016 Pleiades Publishing, Ltd.; Country of input: International Atomic Energy Agency (IAEA); ISSN 1063-7788
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
AUSTENITIC STEELS
BREEDING BLANKETS
FISSILE MATERIALS
FUSION NEUTRON SOURCE FACILITIES
HYBRID SYSTEMS
MAGNETIC FIELDS
MAGNETS
NEUTRON SOURCES
PLASMA FILAMENT
REACTOR VESSELS
SHIELDS
SPENT FUELS
STAINLESS STEELS
STEADY-STATE CONDITIONS
SUPERCONDUCTORS
TOKAMAK DEVICES
TRANSMUTATION