JPS61221694A - Coil for nuclear 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] [Industrial application field] This invention relates to a coil for a nuclear fusion device.

In particular, it relates to a coil crossover and power supply structure for a nuclear fusion device.

[Conventional technology]

Conventional coils for nuclear fusion devices have structures as shown in Figures 3 and 6. (1) is the coil conductor, (1 is the conductor between turns, (Jl is the conductor between the eyebrows, and (ri) is the coil conductor. is the power supply line.

The current flows through the coil conductor (1) &C'G, but the current flows through the turn-to-turn conductor (2), the eyebrow-to-glabel conductor (3), and the feeder line (
In the case of flowing currents, since these are tilted with respect to the assimilation of the coil's arc, an extra current component in directions other than the direction of the coil is generated, which generates an error am harmful to the plasma confinement action of the coil. It was clear that this error magnetic field could be reduced by reducing the area of the loop created by the extra current, so it was considered to change the transition structure.

Figure 7 is a diagram showing the crossing method shown in Japanese Patent Application Laid-Open No. 39-1988-Kuko-t, where (3) is an arrow indicating the direction of the current in the coil;
A) is the cross-glabelled current, C7) is the cross-coil current, (f
f) is a return conductor, which is designed to reduce the error magnetic field by alternately reversing the crossing direction as shown in (6) inside the coil near the plasma (not shown).

[Problem that the invention seeks to solve]

However, even with the conventional technique shown in FIG. 7, the current loop that generates the error magnetic field still remains, and the error magnetic field cannot be canceled out enough, causing the error magnetic field to become a problem. Also, the way it moves between layers is complicated.

There were also production issues.

This invention was made in view of the above-mentioned problems with the conventional technology. It minimizes the error magnetic field by almost eliminating the area of the current loop created by the crossing current, and is designed for use in nuclear fusion devices with good plasma confinement performance. It can also be used for the purpose of obtaining a coil.

[Means for solving problems]

The coil for a nuclear fusion device according to the present invention is characterized in that the return conductor of the coil feeder line is divided into two parts, and the coil main body is externalized, and a part of the return conductor is connected to a resistance and inductance regulator. [Function] Since the resistance and inductance adjuster of the present invention has the function of adjusting the current distribution of the coil return conductor, it is possible to minimize the error magnetic field created by the coil feeding section and the transition section.

〔Example〕

The present invention will be described in detail below with reference to an embodiment shown in the drawings.

This invention has a power feeder configuration kW characteristic, and a coil body (
f) There is one slave conductor (TE) of the feeder line that feeds K, but there is a return conductor (TE) through which the current flows after passing through the coil body (f).
10) is divided into one conductor part (tOa) (tOb)tic, and the part (tOa) outside the coil body (f) of the return conductor (10) is equipped with a resistor and an inductance regulator (11).
) are connected. In Figure 1jli, (l) is the short circuit plate connected to the return conductor portion (tOb''), and (/3) is the plasma.

The current supplied from the slave conductor (?) K of the power supply line flows through the coil body (f), and is transferred from the return conductor (10) IC to the slave conductor (?).
9) Parts on both sides of (tOa) (tab) IIC division [Go back (.

Figure 1 shows the coil shown in Figure 1, ignoring the current in the coil body 11) that generates a normal magnetic field.

This figure schematically shows the cross-over current between the feeder line and the turns inside the coil, which is a cause of the error magnetic field. Current A/ divided into one at the now returning conductor portions (10a) (10b')
Assuming that and LJ are equal, the magnetic fields generated by the current loops of Ll and LJ have the same loop area.

Since they are in opposite directions, they almost cancel each other out, but since the clockwise current loop caused by the Lt current is closer to the plasma (pg
), the magnetic field generated in the plasma region is the current A/
The contribution of these factors has increased slightly.

The difference between the one due to the current ↓l and the one due to AJIC remains as an error magnetic field. Therefore, in order to adjust the current distribution and almost completely cancel out the error magnetic field, a resistor and inductance regulator (11) are installed in the middle of the return conductor. , external to the main body for easy adjustment and replacement.

Figure 3 and reference figures are examples of the case of a two-layer coil.
The figure is a cross-sectional view similar to FIG. 1, and the figure D is a schematic diagram showing the current. Compared to the case of a single layer, the shape and area of the loop depending on the current and bJ are different between the two, so the current distribution is quite different.

The error magnetic field can be canceled in the same manner as in the first and second figures.

The current distribution can be set in advance through calculations, and the magnetic field can be measured after the coil is manufactured to make optimal adjustments.

The above is a two-layer coil [I explained it].

Furthermore, it can also be applied to multi-layered cases. Further, even when a plurality of coils are connected in series, the same effect can be achieved by providing a resistor and an inductance adjuster in the connecting wire between the coils.

〔Effect of the invention〕

As described above, according to the present invention, the return conductor of the coil feeder line is divided into two parts, and a resistance and inductance regulator is provided in the two parts, so that the generation of erroneous hot water discharge is extremely small and the core has good plasma confinement performance. There are effects obtained from the coil for the fusion device.

[Brief explanation of drawings]

FIG. 1 is a cross-sectional view showing the structure of a coil and a power supply line portion of an embodiment of the coil for a nuclear fusion device according to the present invention, and FIG. 1 is a schematic diagram showing the current in the coil of FIG. 1. Figure 3 is a cross-sectional view similar to Figure 1 of the embodiment of the two-layer coil;
FIG. 3 is a schematic diagram showing the current of the coil in FIG. 3, and FIG. 3 is a plan view showing an example of a conventional coil. FIG. 6 is a partial side view seen in the direction of the arrow ■ in FIG. 3. FIG. 7 is a sectional view showing another example of a conventional coil for a nuclear fusion device. In the figure, (S) is the coil body, (?) is the forward conductor, (
10) is a return conductor, (ioa) 1Ob) is a return conductor portion, and (11) is a resistor and inductance regulator. In each figure, the same reference numerals indicate the same or equivalent parts.

Claims (1)

[Claims] A coil for a nuclear fusion device, characterized in that a return conductor of a coil feeding line is divided into two, and a resistor and an inductance regulator are provided on a part of the return conductor outside the coil body.