JPH06308265A - Nuclear fusion device and its operating method - Google Patents

Nuclear fusion device and its operating method

Info

Publication number
JPH06308265A
JPH06308265A JP5097339A JP9733993A JPH06308265A JP H06308265 A JPH06308265 A JP H06308265A JP 5097339 A JP5097339 A JP 5097339A JP 9733993 A JP9733993 A JP 9733993A JP H06308265 A JPH06308265 A JP H06308265A
Authority
JP
Japan
Prior art keywords
plasma
instability
distribution
heating
fusion
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
JP5097339A
Other languages
Japanese (ja)
Inventor
Yasushi Iwai
康 岩井
Kazuhiro Takeuchi
一浩 竹内
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Hitachi Ltd filed Critical Hitachi Ltd
Priority to JP5097339A priority Critical patent/JPH06308265A/en
Publication of JPH06308265A publication Critical patent/JPH06308265A/en
Pending legal-status Critical Current

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Classifications

    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/10Nuclear fusion reactors

Landscapes

  • Plasma Technology (AREA)

Abstract

PURPOSE:To dispense with or simplify a facility for suppressing instability, take a preventive measure for an intra-reactor structure, and improve safety by intentionally inducing the instability of plasma. CONSTITUTION:A plasma measurement diagnostic device 1 obtains the distribution of plasma 3 from the measurement signal of a sensor 2 and outputs it to an arithmetic unit 4. The arithmetic unit 4 judges the instability of the plasma 3 from the data and outputs the control signal to a control device 5. The control device 5 sends an operational instruction to a heating device 6 and interlockingly sends an instruction for the flow adjustment of the cooling water of an intra-reactor structure 8 to a pump 7. The heating device 6 controls the heating of the plasma 3 based on the instruction. An instruction for controlling instability can be sent to the control device 5 from a control console 9.

Description

【発明の詳細な説明】Detailed Description of the Invention

【0001】[0001]

【産業上の利用分野】本発明は核融合装置においてプラ
ズマの不安定性を制御する核融合装置及びその運転方法
に関する。
BACKGROUND OF THE INVENTION 1. Field of the Invention The present invention relates to a fusion device for controlling instability of plasma in a fusion device and a method of operating the same.

【0002】[0002]

【従来の技術】従来の核融合装置では、安定な核融合出
力を得るためにはプラズマの不安定性を抑制する必要が
あるが、それには以下の方法が考えられている。
2. Description of the Related Art In a conventional fusion device, it is necessary to suppress the instability of plasma in order to obtain a stable fusion output, and the following method is considered for that purpose.

【0003】(1)特開昭62−284288号公報に記載のよう
に、プラズマ周辺にポロイダル面内に磁場を作るヘリカ
ル状のコイルへ流す電流を変化させることによって磁気
面を回転させるなど、プラズマの磁気面形状を変化させ
ることによって不安定性の成長を防ぐようになってい
た。
(1) As described in Japanese Patent Application Laid-Open No. 62-284288, the plasma is generated by rotating the magnetic surface by changing the current flowing to a helical coil that creates a magnetic field in the poloidal plane around the plasma. It was supposed to prevent the growth of instability by changing the magnetic surface shape of.

【0004】(2)特開昭60−97291 号公報に記載のよう
に、不安定性の成長している磁気島においてプラズマ電
流を高周波で強制的に駆動するなど、高周波駆動によっ
て不安定性を抑制するようになっていた。
(2) As described in Japanese Patent Application Laid-Open No. 60-97291, the instability is suppressed by high-frequency driving, such as forcibly driving the plasma current at a high frequency on a growing magnetic island of instability. It was like this.

【0005】(3)特開昭62−38387 号公報に記載のよう
に、ペレットをプラズマに打ち込むとペレットが溶けて
プラズマが冷されると同時に燃料がプラズマ中に注入さ
れ密度が上昇するので、これを利用してプラズマの分布
を調整し、不安定性を抑制するようになっていた。
(3) As described in JP-A-62-38387, when pellets are driven into plasma, the pellets are melted and the plasma is cooled. At the same time, fuel is injected into the plasma and the density is increased. Utilizing this, the distribution of plasma was adjusted to suppress instability.

【0006】[0006]

【発明が解決しようとする課題】上記従来の制御方法で
は不安定性を安定化するための制御は難しく、複雑であ
る。例えば、磁場によって不安定性を安定化させる場合
には、通常運転には使用しないヘリカルコイルが新たに
必要である。又、高周波加熱によって不安定性を安定化
させる場合には、磁気島領域に周波数を合わせることが
必要であるが、中心領域で用いるプラズマ点火用のもの
とあわせて二種類必要となる(周波数可変の高周波加熱
装置があれば一種類で充分であるが、現在ではまだ開発
されていない)。又、ペレット入射によって不安定性を
安定化させる場合には、ペレット入射による燃料の量及
び入射方向など微調整が困難である。以上の点から、不
安定性を安定化させようとすると、制御装置が複雑とな
り、信頼性及び安全性に問題があった。
In the conventional control method described above, the control for stabilizing the instability is difficult and complicated. For example, when the instability is stabilized by a magnetic field, a helical coil that is not used for normal operation is newly required. Also, in order to stabilize the instability by high frequency heating, it is necessary to match the frequency to the magnetic island region, but two types are required, including the one for plasma ignition used in the central region (frequency variable). One type is enough if there is a high frequency heating device, but it has not been developed yet). Further, in the case of stabilizing the instability by pellet injection, it is difficult to finely adjust the amount of fuel and the injection direction due to pellet injection. From the above points, when trying to stabilize the instability, the control device becomes complicated and there is a problem in reliability and safety.

【0007】本発明の目的は、装置を簡略化でき、安全
性を向上できる核融合装置とその運転方法を提供するこ
とにある。
An object of the present invention is to provide a fusion device and a method of operating the same which can simplify the device and improve safety.

【0008】[0008]

【課題を解決するための手段】上記目的を達成するた
め、本発明ではプラズマの圧力分布,密度分布、又は温
度分布といった物理量を計測する計測装置を用い、プラ
ズマが不安定性を生じるような分布を呈しているかを演
算器で判断し、制御装置よりプラズマ外部からエネルギ
を与える加熱装置に指令を出して、プラズマの不安定性
を誘起させて飽和させることにより、プラズマの分布形
状を一定に保つプロファイルコンシステンシーの機構を
利用して、不安定性を制御するようにしたものである。
In order to achieve the above object, the present invention uses a measuring device for measuring a physical quantity such as a pressure distribution, a density distribution, or a temperature distribution of plasma to obtain a distribution that causes instability of plasma. It is judged by the calculator whether it is present or not, and the control device issues a command to the heating device that gives energy from outside the plasma to induce the instability of the plasma and saturate it. It is designed to control instability by using the mechanism of tenancy.

【0009】好ましくは、前記加熱装置を作動させるの
と連動させて、炉内構造物への冷却媒体の流量を増加さ
せるように制御し、プラズマ対向面の損傷を軽減し、安
全性を向上できるようにしたものである。
[0009] Preferably, in conjunction with the operation of the heating device, the flow rate of the cooling medium to the furnace internal structure is controlled to increase, damage to the plasma facing surface can be reduced, and safety can be improved. It was done like this.

【0010】[0010]

【作用】プラズマの磁気流体不安定性は、ソーセージ不
安定性,キンク不安定性,交換型不安定性,テアリング
モード不安定性などがある。これらの不安定性が発展し
て飽和すると、プラズマの圧力分布,密度分布、又は温
度分布が、回転変換が有理数となる磁気面(有理面)の
内側で、平坦もしくは勾配の緩やかな一定の分布形状を
保つことが知られている。この性質は、プロファイルコ
ンシステンシーと呼ばれており、不安定性を誘起する加
熱装置には依存しないことがわかっている。例えば、実
験的にはコメンツ プラズマ フィジックス コントラ
クティドフュージョン11(87')63(Comments Pl
asma Phys. Contr. Fusion 11 (1987)63)において、
プロファイルコンシステンシーが加熱装置に依存せずに
成り立っていることが報告されている。また、プラズマ
フィジックス コントラクティド フュージョン32
(90')327(Plasma Phys. Contr. Fusion 32(199
0)327)において、磁気流体不安定性がプロファイルコン
システンシーの機構を駆動させているという数値シミュ
レーションによる研究が報告されている。
[Operation] Magnetohydrodynamic instability of plasma includes sausage instability, kink instability, exchange type instability, tearing mode instability, and the like. When these instabilities develop and become saturated, the plasma pressure distribution, density distribution, or temperature distribution has a flat or gentle gradient distribution shape inside the magnetic surface (rational surface) where the rotational transformation becomes a rational number. Is known to keep. This property is called profile consistency and has been found to be independent of the heating device that induces instability. For example, experimentally, the Comments Plasmas Physics Contracted Fusion 11 (87 ') 63 (Comments Pl
Asma Phys. Contr. Fusion 11 (1987) 63),
It has been reported that the profile consistency is independent of the heating device. In addition, Plasma Physics Contracted Fusion 32
(90 ') 327 (Plasma Phys. Contr. Fusion 32 (199
(0) 327), a numerical simulation study has reported that magnetohydrodynamic instability drives the mechanism of profile consistency.

【0011】そこで、本発明では、計測装置でプラズマ
の分布等を計測しておき、プラズマが不安定性を生じる
ような分布を呈しているかどうかを演算器で判断する。
そしてそれに応じて制御装置より、プラズマ外部からエ
ネルギを与える加熱装置に指令を出して、プラズマの不
安定性を誘起させて飽和させることにより、不安定性を
制御する。その結果、プロファイルコンシステンシーの
機構を利用して、積極的に不安定性を誘起させることに
より、プラズマの圧力分布,密度分布、又は温度分布を
一定の形状に保つことができる。よって、不安定性を抑
制するためのヘリカルコイルや高周波加熱装置ペレット
入射装置などの装置及び制御機構が、不要又は簡単化で
きるので、核融合装置の構成を簡略化でき、信頼性を向
上させることができる。
Therefore, in the present invention, the plasma distribution and the like are measured by the measuring device, and the arithmetic unit determines whether or not the plasma has a distribution that causes instability.
In response to this, the control device issues a command from the outside of the plasma to the heating device to induce the instability of the plasma and saturate it, thereby controlling the instability. As a result, it is possible to maintain the pressure distribution, the density distribution, or the temperature distribution of the plasma in a constant shape by positively inducing the instability by utilizing the profile consistency mechanism. Therefore, a device such as a helical coil or a high-frequency heating device pellet injection device for suppressing instability and a control mechanism can be unnecessary or simplified, so that the configuration of the fusion device can be simplified and reliability can be improved. it can.

【0012】好ましくは、不安定性を誘起すると熱流束
が増すので、予め炉内構造物への冷却媒体の流量が増す
ようにしておき、安全性を向上させることができる。
[0012] Preferably, instability induces an increase in heat flux, so that the safety can be improved by increasing the flow rate of the cooling medium to the internal structures in advance.

【0013】[0013]

【実施例】以下、本発明の実施例を図1により説明す
る。図1は、本発明の実施例になる核融合装置の基本的
な構成を示したものである。プラズマ計測診断装置1
は、センサ2の計測信号から、プラズマ3の圧力分布P
(r),密度分布n(r)、又は温度分布T(r)等(ここで
rはトーラス断面の中心からの位置を示している。)を
求め、演算器4に出力する。演算器4では、それらプラ
ズマの分布等のデータからプラズマの不安定性を判断
し、プラズマが不安定な分布を示して不安定性制御が必
要と判断した場合等、プラズマの状態に応じて制御装置
5へ制御信号を出力する。制御装置5は、制御信号に基
づき、不安定性を誘起する加熱装置6の作動に関する指
令を出力する。又、制御装置5は、加熱装置6に指令を
出力するのと連動させて、炉内構造物8の熱除去を行っ
ている冷却水の流量調節のための指令をポンプ7へ出力
する。加熱装置6は、指令に基づきプラズマ3への加熱
の制御を行う。又、運転員が、核融合出力の調節などの
ために、制御卓9から制御装置5へ不安定性制御の指令
を出力できる。
DETAILED DESCRIPTION OF THE PREFERRED EMBODIMENTS An embodiment of the present invention will be described below with reference to FIG. FIG. 1 shows a basic configuration of a nuclear fusion device according to an embodiment of the present invention. Plasma measurement diagnostic device 1
Is the pressure distribution P of the plasma 3 from the measurement signal of the sensor 2.
(r), density distribution n (r), temperature distribution T (r), etc. (where r indicates the position from the center of the torus cross section) are obtained and output to the calculator 4. The computing unit 4 determines the instability of the plasma from the data of the plasma distribution and the like, and when the instability control of the plasma is shown and it is determined that the instability control is necessary, the control device 5 is operated according to the state of the plasma. Output a control signal to. The control device 5 outputs a command regarding the operation of the heating device 6 that induces instability based on the control signal. Further, the control device 5 outputs a command to the pump 7 for adjusting the flow rate of the cooling water for removing the heat of the in-core structure 8 in conjunction with outputting the command to the heating device 6. The heating device 6 controls heating of the plasma 3 based on the command. Further, the operator can output an instability control command from the control console 9 to the control device 5 in order to adjust the fusion output.

【0014】プラズマ計測診断には以下の方法を用い
る。圧力分布を求めるのには、軟X線の放射強度計測を
用い、電子温度及び電子密度を求めるのには、プラズマ
にレーザ光を通して、トムソンレーザ散乱の、散乱光の
波長広がりと散乱強度をそれぞれ用いる。
The following method is used for plasma measurement diagnosis. The radiation intensity measurement of soft X-ray is used to obtain the pressure distribution, and the electron temperature and the electron density are obtained by passing the laser light through the plasma to determine the wavelength spread and the scattering intensity of the scattered light of Thomson laser scattering, respectively. To use.

【0015】加熱装置には、粒子入射装置と高周波加熱
装置を用いる。粒子入射装置には、NBI(中性粒子入
射装置),負イオン入射装置があり、高周波加熱装置に
は、ECH(電子サイクロトロン周波数帯加熱),IC
H(イオンサイクロトロン周波数帯加熱),LHH(低
域混成波周波数帯加熱)がある。
As the heating device, a particle injection device and a high frequency heating device are used. Particle injectors include NBI (neutral particle injector) and negative ion injectors, and high frequency heating devices include ECH (electron cyclotron frequency band heating) and IC.
There are H (ion cyclotron frequency band heating) and LHH (lower hybrid wave frequency band heating).

【0016】本実施例によれば、不安定性を安定化する
ための設備が不要となるので、核融合装置の構造を単純
にすることができる。不安定性が成長して飽和すると、
プラズマのエネルギの一部が外に出ていくので、いつ不
安定性が成長して飽和するかがわからなければ、炉内構
造物がそれに耐えられるだけの冷却能力を、常時、保っ
ておかなければならない。しかし、本実施例のようにプ
ラズマの不安定性を作為的に誘起することにすれば、そ
の時に合わせてポンプの出力を上げれば良いので、炉内
構造物の安全性を高めることできる。又、ポンプの通常
出力は下げておいて、不安定性を誘起する時にのみ一時
的にポンプの出力を上げることにより、炉内構造物に対
する安全性を充分確保できるので、冷却設備の規模縮小
及びコストの低減を図ることができる。
According to the present embodiment, the equipment for stabilizing the instability is not required, so that the structure of the fusion device can be simplified. When the instability grows and saturates,
Some of the plasma's energy goes out, so if you don't know when the instability grows and saturates, you should always keep the cooling capacity of the reactor internals to withstand it. I won't. However, if the instability of the plasma is artificially induced as in this embodiment, the output of the pump may be increased at that time, so that the safety of the reactor internal structure can be improved. Also, by lowering the normal output of the pump and temporarily increasing the output of the pump only when instability is induced, it is possible to ensure sufficient safety for the internal structures of the reactor. Can be reduced.

【0017】[0017]

【発明の効果】本発明によれば、不安定性を抑制するた
めの設備を不要にすることができる。又、プラズマの不
安定性を作為的に誘起するので、炉内構造物に対して予
防措置を講じる事ができ、安全性を高めることができ
る。
According to the present invention, equipment for suppressing instability can be eliminated. In addition, since the instability of plasma is artificially induced, it is possible to take preventive measures against the internal structure of the furnace and enhance the safety.

【図面の簡単な説明】[Brief description of drawings]

【図1】本発明の一実施例の核融合装置の基本的な構成
を示したブロック図。
FIG. 1 is a block diagram showing a basic configuration of a nuclear fusion device according to an embodiment of the present invention.

【符号の説明】[Explanation of symbols]

1…プラズマ計測診断装置、2…センサ、3…プラズ
マ、4…演算器、5…制御装置、6…加熱装置、7…ポ
ンプ、8…炉内構造物、9…制御卓。
DESCRIPTION OF SYMBOLS 1 ... Plasma measuring / diagnosing device, 2 ... Sensor, 3 ... Plasma, 4 ... Computing device, 5 ... Control device, 6 ... Heating device, 7 ... Pump, 8 ... Reactor internals, 9 ... Control console.

Claims (5)

【特許請求の範囲】[Claims] 【請求項1】核融合炉の炉心のプラズマを制御しつつ運
転する方法において、前記プラズマに不安定性を誘起す
ることにより、前記プラズマの分布形状を一定に保つプ
ロファイルコンシステンシーの機構を利用して、前記プ
ラズマの圧力分布,密度分布、又は温度分布を制御する
ことを特徴とする核融合装置の運転方法。
1. A method of operating while controlling the plasma of the core of a fusion reactor, utilizing a profile consistency mechanism for maintaining a constant distribution profile of the plasma by inducing instability in the plasma. A method for operating a fusion device, comprising controlling the pressure distribution, density distribution, or temperature distribution of the plasma.
【請求項2】請求項1において、前記プラズマに不安定
性を誘起させる加熱源として、粒子入射装置又は高周波
加熱装置を用いて制御する核融合装置の運転方法。
2. The method of operating a nuclear fusion device according to claim 1, wherein a particle injection device or a high frequency heating device is used as a heating source for inducing instability in the plasma.
【請求項3】核融合装置において、プラズマの物理量を
計測する計測診断装置と、前記計測診断装置の信号に基
づいて前記プラズマに不安定性を誘起させる加熱装置を
有することを特徴とする核融合装置。
3. A fusion device, comprising: a measurement / diagnosis device for measuring a physical quantity of plasma; and a heating device for inducing instability in the plasma based on a signal from the measurement / diagnosis device. .
【請求項4】請求項1において、不安定性を誘起させる
のと連動させて、炉内構造物への冷却媒体の流量を制御
する核融合装置の運転方法。
4. The method of operating a nuclear fusion device according to claim 1, wherein the flow rate of the cooling medium to the internal structure is controlled in conjunction with inducing instability.
【請求項5】請求項3において、前記加熱装置を作動さ
せるのと連動させて、炉内構造物への冷却媒体の流量を
制御する制御装置を有する核融合装置。
5. The fusion device according to claim 3, further comprising a controller for controlling the flow rate of the cooling medium to the internal structure of the reactor in association with the operation of the heating device.
JP5097339A 1993-04-23 1993-04-23 Nuclear fusion device and its operating method Pending JPH06308265A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
JP5097339A JPH06308265A (en) 1993-04-23 1993-04-23 Nuclear fusion device and its operating method

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
JP5097339A JPH06308265A (en) 1993-04-23 1993-04-23 Nuclear fusion device and its operating method

Publications (1)

Publication Number Publication Date
JPH06308265A true JPH06308265A (en) 1994-11-04

Family

ID=14189729

Family Applications (1)

Application Number Title Priority Date Filing Date
JP5097339A Pending JPH06308265A (en) 1993-04-23 1993-04-23 Nuclear fusion device and its operating method

Country Status (1)

Country Link
JP (1) JPH06308265A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN117454301A (en) * 2023-12-22 2024-01-26 深圳大学 Method and system for displaying change of PV value tracked by nuclear fusion test

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN117454301A (en) * 2023-12-22 2024-01-26 深圳大学 Method and system for displaying change of PV value tracked by nuclear fusion test
CN117454301B (en) * 2023-12-22 2024-04-16 深圳大学 Method and system for displaying change of PV value tracked by nuclear fusion test

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