The main physical and engineering problems in creating a tokamak with a strong magnetic field and adiabatic compression of the plasma

Azizov, Eh.A.; Alekseev, Yu. A.; Brevnov, N. N.; Velikhov, E. P.; Glebov, I. A.; Glukhikh, V. A.; Demichev, V. F.; Kadomtsev, B. B.; Karasev, B.G.; Krylov, V. A.; Larionov, B.A.; Malyshev, I. F.; Mozin, I.V.; Monoszon, N.A.; Odintsov, V. I.; Pis'mennyǐ, V. D.; Putvinskii, S.V.; Рутберг, Ф. Г.; Spirchenko, Yu.V.; Stolov, A.M.; Chuyanov, V.A.

doi:10.1007/bf01138919

Cited by 3 publications

(7 citation statements)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…). It is a step on the way to the fusion power engineering, which goes through the plasma production and confinement in the high magnetic field and is underlaid by the experiments at such facilities as T-14 [19], FTU [20], and Alcator C-Mod [21] and such projects as CIT [22], Ignitor [23], DTT [24], and SPARC [25]. The basic TRT conceptual design parameters are shown in Table 1 in comparison with those of other facilities and projects.…”

Section: Trt Concept and Missionsmentioning

confidence: 99%

Tokamak with Reactor Technologies (TRT): Concept, Missions, Key Distinctive Features and Expected Characteristics

Krasilnikov¹,

Коновалов

Bondarchuk

et al. 2021

Plasma Phys. Rep.

View full text Add to dashboard Cite

Important progress in the development of high-temperature superconductors (HTSC) of the second group made it possible to design the quasi-stationary tokamak with reactor technologies (TRT) with the high magnetic field (B t0 = 8 T). The high magnetic field will ensure the achievement of plasma fusion regimes in the tokamak with the fusion energy gain Q > 1 at the considerably reduced size of the facility (R 0 = 2.15 m, a = 0.57 m), and, consequently, at its reduced cost. TRT will be capable of operating in the quasi-stationary regimes (≥100 s) with hydrogen, helium, and deuterium plasmas (with the densities n e of up to 2 × 10 20 m -3 ) and in the regimes with short (duration Δt < 10 s) deuterium-tritium plasma shots with the fusion energy gain Q > 1 limited by the radiation heating of toroidal coils. TRT is being designed as a plasma prototype for both the pure fusion reactor and the fusion neutron source for the hybrid (fusion-fission) reactor. The TRT missions are the development of the key fusion technologies and their integration in one facility. These technologies are as follows: the HTSC electromagnetic system operating at the extremely high magnetic fields; the metal and liquid-metal (lithium) first wall and innovative divertor; the unique advanced systems for the auxiliary plasma heating and non-inductive current drive, including the systems for atomic beam injection with energy of 0.5 MeV and power of several tens of megawatts, the electron cyclotron heating system based on the megawatt-power gyrotrons with a frequency of 230 GHz and a total power of ~10 MW, and the ion cyclotron heating system at frequencies of 60-80 MHz with a power of several megawatts; the tritium fuel cycle; the remote control technologies; the technologies for diagnostics capable of operating under the fusion reactor conditions; the technologies for maintaining quasi-stationary plasma discharges; and the technologies for the tokamak operation in the fusion ignition regime, in which the heating by alpha particles is the dominant heating mechanism at the axis of the plasma column, in the deuterium-tritium experiments limited by the radiation heating of the toroidal coils. The results are presented from the conceptual design of the basic TRT components, as well as the expected characteristics of its operation. It is shown that TRT has a wide window of working parameters suitable for studying the reactor operating regimes. The high magnetic field provides the necessary margins of the pressure, MHD stability, and plasma controllability variation. Implementation of the advanced divertor and first wall concepts, including those using the liquid-metal technologies, will provide the optimum choice of design options in order to reliably control the heat and particle fluxes under the reactor conditions. The advanced systems for the auxiliary heating and current drive will make it possible to implement both the pulsed and stationary regimes of the reactor operation. Calculations of the TRT discharge scenarios show that, for the DT mixture with...

show abstract

Section: Trt Concept and Missionsmentioning

confidence: 99%

Tokamak with Reactor Technologies (TRT): Concept, Missions, Key Distinctive Features and Expected Characteristics

Krasilnikov¹,

Коновалов

Bondarchuk

et al. 2021

Plasma Phys. Rep.

View full text Add to dashboard Cite

show abstract

“…It should be noted that only the first two are under construction, T-14 is under development, while the remaining are design proposals, which are included in order to give an idea of the options for HFT. Here, K is the elongation factor of the cross-section, C R and C a are the major and minor compression ratios (where 6) toroidal magnetic accumulator [33].…”

Section: Planned High Field Tokamaksmentioning

confidence: 99%

“…T-14 1 [31][32][33] is under development (tests of components) at the Kurchatov Institute (Moscow) (Fig. 2.5); it uses strong adiabatic compression in order to produce high density, high temperature plasma.…”

Section: Planned High Field Tokamaksmentioning

confidence: 99%

High magnetic field tokamaks

et al. 1986

View full text Add to dashboard Cite

A review of existing high magnetic field tokamaks is presented. The results obtained, especially in the research areas concerning confinement, impurity control and heating, are discussed and compared with those of tokamaks at lower toroidal field. New devices, either proposed or under construction, are surveyed. Advantages and difficulties of such machines in exploring the approach to ignition are examined.

show abstract

“…For X < A, i.e. for large velocities when the chamber wall thickness is much greater than the skin depth, we have J 2 ' " '…”

Section: ! = F [Vxb]+?5(x)5(y)mentioning

confidence: 99%

“…Since it is desirable that the plasma transport takes less time than the energy confinement time TE > this limitation can be of importance to small tokamaks [2,3] with strong fields and nr£~ 10 15 cm" 3 *s after compression: at high voltages it will be difficult to build thin chambers which would be able to withhold great loads.…”

Section: Introductionmentioning

confidence: 99%

Effect of conducting vacuum chamber on the compression along the major radius of a tokamak plasma column

Zhogolev

Putvinskij

1982

Nucl. Fusion

View full text Add to dashboard Cite

The paper considers the effect of a thin conducting vacuum chamber on the movement of the plasma column in a tokamak during plasma compression in the direction of the major radius. It is shown that a sort of frictional force acts on the plasma column from the direction of the vacuum chamber. The maximum value of this force per unit length can be considerable: F m a x = J 2 /(ac 2 \/2 ), where J is the plasma current and a is the distance from the plasma centre to the side wall of the chamber. A study of the dynamics of the plasma column motion shows that in the presence of a vacuum chamber the displacement velocity of the column is bounded by the value V, =c 2 /(2\/2 no A), where A is the thickness and a the conductivity of the chamber wall. If the velocity rises above the critical value, the compression is accompanied by the development of self-oscillations.

show abstract

The main physical and engineering problems in creating a tokamak with a strong magnetic field and adiabatic compression of the plasma

Cited by 3 publications

References 1 publication

Tokamak with Reactor Technologies (TRT): Concept, Missions, Key Distinctive Features and Expected Characteristics

Tokamak with Reactor Technologies (TRT): Concept, Missions, Key Distinctive Features and Expected Characteristics

High magnetic field tokamaks

Effect of conducting vacuum chamber on the compression along the major radius of a tokamak plasma column

Contact Info

Product

Resources

About