JPS6080787A - Torus-shaped fusion device - Google Patents

Abstract

(57) [Summary] This bulletin contains application data before electronic filing, so abstract data is not recorded.

Description

DETAILED DESCRIPTION OF THE INVENTION [Field of Application of the Invention] The present invention relates to a toroidal fusion stack kK in which a toroidal magnetic field coil for confining plasma in a plasma container is formed of superconducting coils.

[Background of the invention]

FIG. 1 is a longitudinal sectional view of a conventional torus-shaped fusion device 6.0. An annular plasma container 2 that can contain 1 J of ultra-high temperature plasma 1 is maintained in a high vacuum state inside. Around the outer periphery of this plasma container 2, toroidal magnetic field coils 3 consisting of several 11L conductive coils that generate a magnetic field for plasma confinement are arranged at equal intervals so as to form a torus shape as a whole. These toroidal magnetic field coils 3 are supported by an upper pace 4 and a lower base 5, and an internal voloidal magnetic field coil 6 and an external voloidal magnetic field coil 7, which generate a vertical magnetic field for plasma indexing 1, are attached to the plasma vessel. 2 and the toroidal moth field coil 3, and above and below the frame 8 (
There is. Further, a current transformer coil 9 for heating the plasma 1 confined within the plasma container 2 is mounted around the central main column 10.

In this way, in the torus-shaped core, a normal conducting coil has conventionally been used as the toroidal magnetic field coil, but from the viewpoint of increasing the toroidal magnetic field to be generated and reducing the amount of electric power used, it has recently been It is desired to use a super-furrowed coil.

By the way, in the toroidal fusion reactor, the plasma in the plasma reactor is controlled together with the toroidal magnetic field coil.
The only thing missing is the installation of a boroidal mountain coil.

However, when a toroidal magnetic field coil is made into a superconducting type, this superconducting coil has an extremely low crystalline (42°IO) and a voloidal (MW coil is at room temperature, and is maintained in a high vacuum state). The plasma in the plasma reactor is extremely high temperature, so in order to make the troutal coil into an extremely low groove and keep it in a very poor condition, the plasma in the plasma reactor is extremely hot. This is a major issue, and the thermal radiation shields used in the Super 7!4 device generally use steel plates, aluminum plates, etc. that have a good heat transfer rate for heat balance.However, in the torus-shaped fusion device, As mentioned above, it is equipped with a group of voloidal magnetic field coils to stabilize the plasma, and these poloidal 1h field coils are passed through in a pulsed manner.
It is necessary to cause the magnetic field generated by this to act on the plasma. When using a copper plate or aluminum plate with a good rate of heat conduction, which has been commonly used in the past, it is necessary to use a voloidal magnetic coil (W field is heat conduction). It is shielded from the enemy by the j+'+mugi shield and no longer affects plasma.

In other words, when using a thermal radiation shield with good energy transmission, IAt is generated in the A radiation shield due to the heat of the voloidal ++b k'J coil, and the resulting repulsive magnetic field acts on the plasma. This is considered to be a drawback in that the tI94 field becomes weak and the magnetic field of the voloidal magnetic field coil does not work effectively.

[Purpose of emitting ψ]

The present invention was made in consideration of this point, and its purpose is to bring an ultra-1Jf toroidal magnetic field coil to an extremely low temperature.
It is an object of the present invention to provide a torus-shaped nuclear fusion device that can stably control a plasma by effectively acting on the plasma with a magnetic field generated by a voloidal field coil.

[It's the first day of work! ↓L Required] To achieve this purpose, the present invention is extremely useful! Of the heat radiation shield provided surrounding the Toroidal M J19 coil, there is a small amount of 1. c Spider Plasma K 4. Another feature is that the adjacent thermal radiation shield is made of electrically high resistance material. Preferred implementation of the present invention 4j3? In this case, the heat radiation law shield is divided into several grains and the voloidal 0
14% vortex caused by coil'v1. Further suppressing the occurrence of water flow and reducing the number of times in history! A mountain 7 air insulation proboscis is placed on the r11 part.
and heat shield.

[Examples of inventions]

Hereinafter, an embodiment of the present invention will be explained in detail with respect to 2nd t&1 to 1st to s1. In addition, in these figures, the numbers on the right as in Figure 1 indicate the same or equivalent items.

The difference between this embodiment and the conventional example shown in Fig. 1 is that the toroidal magnetic field coil is replaced by a superconducting coil cooled to an ultra-low temperature by liquid helium, instead of the conventional normal-conducting coil.
1 is used, and this ultra-thin toroidal magnetic field coil 11
In order to maintain the superconducting toroidal magnetic field coil 11 at an extremely low temperature, an annular thermal radiation shield tube 12 is installed within the diameter of the superconducting toroidal magnetic field coil 11, and an inner PA is installed so as to bend it outward of the superconducting toroidal magnetic field coil 11. A radiation shield tube 3, an outer heat radiation shield tube 14, an upper 11+lI heat radiation shield link 15, and a lower Cfil heat width shield ring 16 are provided, respectively, and the entire equipment is covered with an insulating vacuum container 17 to maintain a vacuum state. It is maintained in In addition,
The radiation shield is equipped with a cooling pipe, and is activated by flowing liquid nitrogen through it.

Therefore, heat intrusion from the outside of the device is prevented by
Most of the heat that has penetrated from the outside to the inside of the vacuum vessel 17 and the radiant heat generated by the external voloidal magnetic field coil 7 and the variable θ1 coil 9 are blocked by the inner and outer heat radiation shield cylinders. 13 , 14 and the upper and lower heat radiation shield rings 15 , 16 , and furthermore, the radiant heat from the plasma container 2 , which confines ultra-high temperature plasma L, and the internal voloidal magnetic field coil 6 is blocked by the heat radiation shield tube 12 . Therefore, the superconducting toroidal tapping coil 11 must be kept at an extremely low temperature.
Become.

Also, as a cleaning material for each of the heat radiation shields mentioned above.

It is desirable to use a material with high air resistance and good heat shielding, such as stainless steel or aluminum. As shown in FIGS. 3 and 4, the heat radiation shield J2, which is disposed closest to the plasma vessel, is divided into K and K in the circumferential direction of the large diameter of the torus, and each divided part is 12
Between a and 1, there is a break consisting of a synthetic resin layer and insulation layer + mH.
A shaped spacing piece 18 is inserted.

Therefore, the fr of valley holoidal research field coil 6.7 etc.
Vortex 1 imp generated in each thermal excavation shield by R field
, is reduced by 11~in, and the plasma can be stabilized by allowing the magnetic field generated by the poloidal magnetic field coil to act on the plasma IK moon effect.

〔Effect of the invention〕

As explained above, according to the present invention, the fourth aspect of the present invention is that although a superconducting coil is used as the toroidal magnetic field coil, it can be maintained at an extremely low temperature (if), and the voloidal h! t'
Plasma can be stably controlled (tll') by effectively applying the magnetic field generated by the four coils to the no-lasma.

[Brief explanation of drawings]

Figure 1 shows a vertical view of a conventional torus-shaped fusion device [opening], Figure 2 shows a vertical 1θr view of a torus-shaped fusion device according to an embodiment of the present invention, and Figure 3 shows a thermal radiation shield tube. plan view of
FIG. 4 is an enlarged view of part A in FIG. 3. 2...Plasma u 6% 6,7...
Voloidal magnetic field coil% 11...Superconducting toroidal magnetic field coil, 12-16...mb II
MIl fire shield. 1st Store Figure 2 16 5 / Figure 3

Claims (1)

[Claims] 1. An annular plasma vessel whose interior is kept in a high vacuum state, a superconducting toroidal magnetic field coil that confines plasma generated within the plasma vessel, and a voloidal coil that controls the plasma. A thermal radiation shield is provided surrounding the toroidal magnetic field coil so as to maintain the toroidal magnetic field coil at an extremely low temperature, and of the thermal radiation shield, at least a thermal radiation shield closest to the plasma is provided. A set of torus-shaped nuclear fusion equipment characterized by the fact that the shield is made of electrically high resistance material. 2. Scope of Claims No. 1. In lI′J, +iiJ
The thermal radiation shield closest to the plasma is formed into an annular shape by taking 1+1j of the MiJ plasma containers, and is divided into bales anfA along the large diameter circumferential direction. Torus-shaped fusion device Q. 3% The torus-shaped nuclear fusion device 4t according to claim 2, characterized in that an electrical insulator is disposed between the divided parts of the thermal radiation shield to provide thermal shielding.