CN114360747B - Tokamak plasma rupture real-time control and mitigation system and method - Google Patents
Tokamak plasma rupture real-time control and mitigation system and method Download PDFInfo
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- CN114360747B CN114360747B CN202111551974.5A CN202111551974A CN114360747B CN 114360747 B CN114360747 B CN 114360747B CN 202111551974 A CN202111551974 A CN 202111551974A CN 114360747 B CN114360747 B CN 114360747B
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Abstract
The invention belongs to the field of controllable nuclear fusion, and particularly relates to a system and a method for controlling and relieving plasma fracture of a Tokamak in real time.
Description
Technical Field
The invention belongs to the field of controllable nuclear fusion, and particularly relates to a system and a method for controlling and relieving plasma fracture of tokamak in real time.
Background
Plasma rupture is an unavoidable phenomenon of tokamak devices, which poses a serious threat to the safe operation of the device. The destructive nature of plasma cracking increases exponentially with increasing device size and parameters, and for future large tokamak fusion stacks, a single plasma rupture can lead to serious device damage.
The rapid decay of the plasma current during the rupture induces a very large circumferential electric field which can lead to the generation of high flux of high energy escaping electrons whose loss of the strike device first wall will cause melting damage to the apparatus.
At the same time, the plasma current and thermal energy will bombard directly onto the device first wall, which will be subjected to a large thermal deposition, while part of the plasma current enters the device first wall and forms a corona current at the first wall, whereby the device will be subjected to a large electromagnetic force.
Plasma rupture thus poses a serious threat to the safe operation of tokamak devices. Moreover, the destructive nature of plasma rupture increases exponentially with increasing device size and parameters, for example, for international thermonuclear reactor devices ITER, 360MJ of heat will be deposited on the device first wall during rupture, the device as a whole will withstand tens of thousands of tons of electromagnetic force, the escaping electron energy is up to 100MeV, and the escaping electron beam carries 180MJ of energy. The ITER is seriously damaged by one-time plasma rupture.
Therefore, plasma rupture must be controlled and mitigated to reduce its destructive nature and ensure safe operation of the device.
At present, the Tokamak plasma rupture control and release adopts preset system trigger time, and does not have real-time control and release functions, so that corresponding control and release cannot be implemented in real time according to the stage and state of plasma rupture, and therefore, the control and release effects and success rate are poor, and an ideal state cannot be achieved.
Disclosure of Invention
The invention aims to provide a system and a method for controlling and relieving plasma fracture in real time, which can realize the control and the relief of the plasma fracture in real time and effectively relieve the plasma fracture phenomenon in a tokamak device.
The technical scheme of the invention is as follows:
the Tokamak plasma fracture real-time control and relief system comprises a plasma diagnosis data real-time acquisition system, a plasma fracture intelligent early warning algorithm module, a central processing system, a fracture avoidance system, a thermal deposition and corona current relief system, a fracture escape electron avoidance system, a fracture escape electron relief system and a plasma fracture control and relief termination system;
the plasma diagnosis data real-time acquisition system transmits the high-space-time resolution measurement data related to plasma fracture to the intelligent early warning algorithm module for plasma fracture;
the intelligent early warning algorithm module for plasma fracture carries out rapid real-time identification and early warning on plasma fracture and transmits early warning information to the central processing system;
the central processing system sends a starting instruction to the rupture avoidance system;
the rupture avoidance system successfully prevents the rupture, and then sends an end task instruction to the plasma rupture control and relief termination system;
if the rupture avoidance system does not successfully prevent rupture, a start instruction is sent to the thermal deposition and corona current mitigation system and the rupture escape electronic avoidance system at the same time;
the thermal deposition and corona current mitigation system achieves mitigation of thermal deposition and corona currents generated during plasma rupture;
the rupture escape electron avoids the system from consuming an escape "seed" electron, wherein:
if the avoidance of the broken escaping electrons is successfully realized, a task ending instruction is sent to a plasma break control and release termination system;
if the generation of the cracking escape electrons is not successfully prevented, starting a cracking escape electron mitigation system;
the cracking escape electron relieving system dissipates the cracking escape electrons until the cracking escape electron is successfully avoided, and then a task ending instruction is sent to the plasma cracking control and relieving termination system.
The thermal deposition and corona current relieving system injects inert gas into the plasma, wherein the volume of the injected gas is ten times that of background plasma, and thermal deposition and corona current generated during plasma rupture are relieved.
The rupture escape electron avoidance system consumes escaping "seed" electrons when the plasma core produces a strong magnetic disturbance.
The strong magnetic disturbance isThe magnetic field disturbance amplitude is B, and the circumferential magnetic field intensity of the plasma is B.
The rupture escape electron mitigation system injects argon into the plasma core, dissipating the rupture escape electrons.
The injection volume of the argon gas is ten times that of background plasma.
In the system for acquiring the plasma diagnosis data in real time, the diagnosis and resolution time of plasma fracture is 0.1-1ms, and the spatial resolution length of the section diagnosis data reaches 0.1-10cm.
In the intelligent early warning algorithm module for plasma fracture, a neural network algorithm is utilized to train plasma discharge data.
In the rupture escape electronic avoidance system, the measurement precision of the magnetic islands of the instability of the magnetic fluid is less than 1cm; the magnetic fluid instability suppression time is less than 30ms; the rupture avoidance system reaction time is less than 1ms.
The method for controlling and relieving the plasma fracture of the tokamak in real time is based on the system for controlling and relieving the plasma fracture of the tokamak in real time and comprises the following steps:
step 1), a plasma diagnosis data real-time acquisition system transmits high-time-space resolution measurement data related to plasma fracture to a plasma fracture intelligent early warning algorithm module;
step 2), the intelligent early warning algorithm module for plasma fracture rapidly and real-timely recognizes and early warns the plasma fracture, and transmits early warning information to the central processing system;
step 3), according to the rapid identification and early warning information of plasma fracture sent by the fracture intelligent early warning algorithm module, the central processing system sends a starting instruction to the fracture avoiding system: if the fracture is successfully prevented from being avoided, completing the task, and if the fracture is not successfully prevented from happening, starting a thermal deposition and corona current relieving system and a fracture escape electronic avoiding system at the same time;
step 4), the thermal deposition and corona current relieving system injects inert gas into the plasma, wherein the volume of the injected gas is ten times that of background plasma, so that thermal deposition and corona current generated during plasma rupture are relieved;
step 5), when the strong magnetic disturbance is generated by the plasma core, the cracking escape electron avoiding system consumes escaping seed electrons, if the cracking escape electron avoiding is successfully realized, the task is completed, and if the cracking escape electron is not successfully prevented from being generated, the cracking escape electron relieving system is started;
step 6), after the rupture escape electron mitigation system is started, a large amount of argon is injected into the plasma core part by the rupture escape electron mitigation system, so that the rupture escape electrons are dissipated, and the task is completed.
The plasma diagnosis data real-time acquisition system is used for transmitting measurement data for identifying the fracture to the intelligent early warning algorithm module in real time, and the intelligent early warning algorithm module is used for rapidly identifying and early warning the plasma fracture in real time and then transmitting early warning information to the central processing system.
The plasma fracture control and mitigation is realized by a central processing system, a fracture avoidance system, a thermal deposition and corona current mitigation system, a fracture escape electron avoidance system, a fracture escape electron mitigation system and a plasma fracture control and mitigation termination system together, and the process is as follows:
after the central processing system receives the rupture early warning information, firstly, sending an opening instruction to the rupture avoidance system, and if the rupture avoidance is successfully realized, completing the task; if the occurrence of cracking is not successfully prevented, the thermal deposition and corona current mitigation system and the cracking escape electron avoidance system are activated simultaneously.
The thermal deposition and corona current mitigation system, the rupture escape electron mitigation system and the plasma rupture control and mitigation termination system together achieve the mitigation of plasma rupture escape electrons by the following processes:
when the occurrence of plasma rupture is not realized, the thermal deposition and corona current relieving system receives a starting instruction, and a large amount of inert gas is injected into the plasma to relieve the ruptured thermal deposition and corona current;
when the generation of the cracking escape electrons is not realized, the cracking escape electron relieving system receives a starting instruction, and injects a large amount of argon into the plasma core to relieve the cracking escape electrons;
after the breaking escape electron relieving system is completed, a completed instruction is sent to the plasma breaking control and relieving terminating system, and the plasma breaking control and relieving terminating system terminates all tasks of the plasma breaking real-time control and relieving, and sends the completed instruction to the central processing system.
The invention has the following remarkable effects:
the invention realizes the real-time control and alleviation of plasma fracture by combining the intelligent plasma fracture early warning technology and the accurate fracture control and alleviation technology.
According to the scheme, the plasma fracture early warning system carries out real-time identification and early warning on plasma fracture through the diagnosis data real-time acquisition system, and the central processing system sends instructions to the fracture avoiding system and the fracture relieving system after receiving the fracture early warning, so that the plasma fracture is avoided or relieved. The plasma cracking control device can effectively control and relieve plasma cracking, ensures the safe operation of the device, and is very suitable for real-time control and relieving of tokamak plasma cracking.
Drawings
FIG. 1 is a schematic diagram of a Tokamak plasma break real-time control and mitigation system;
in the figure: the system comprises a 1-plasma diagnosis data real-time acquisition system, a 2-plasma fracture intelligent early warning algorithm module, a 3-central processing system, a 4-fracture avoiding system, a 5-heat deposition and corona current relieving system, a 6-fracture escape electron avoiding system, a 7-fracture escape electron relieving system and an 8-plasma fracture control and relieving termination system.
Detailed Description
The invention is further illustrated by the following figures and detailed description.
The system comprises: the plasma diagnosis data real-time acquisition system 1, the plasma fracture intelligent early warning algorithm module 2, the central processing system 3, the fracture avoidance system 4, the thermal deposition and corona current mitigation system 5, the fracture escape electron avoidance system 6, the fracture escape electron mitigation system 7 and the plasma fracture control and mitigation termination system 8.
The plasma diagnosis data real-time acquisition system 1 transmits the high-space-time resolution measurement data related to plasma fracture to the intelligent early warning algorithm module 2 for plasma fracture;
the intelligent early warning algorithm module 2 for plasma fracture carries out rapid real-time identification and early warning on the plasma fracture and transmits early warning information to the central processing system 3;
according to the rapid identification and early warning information of the plasma fracture sent by the fracture intelligent early warning algorithm module 2, the central processing system 3 sends a starting instruction to the fracture avoiding system 4: if the fracture avoidance is successfully prevented, completing the task, and if the fracture is not successfully prevented, starting the thermal deposition and corona current relieving system 5 and the fracture escape electronic avoiding system 6;
the thermal deposition and corona current relieving system 5 injects inert gas into the plasma, wherein the volume of the injected gas is ten times that of background plasma, so that the thermal deposition and corona current generated during the plasma rupture is relieved;
the crack escape electron avoiding system 6 generates strong magnetic disturbance on the plasma coreFor the magnetic field disturbance amplitude, B is the circumferential magnetic field intensity of the plasma), escape "seed" electrons are consumed, if the avoidance of the crack escape electrons is successfully realized, the task is completed, if the generation of the crack escape electrons is not successfully prevented, the crack escape electron mitigation system 7 is started;
after the rupture escape electron mitigation system 7 is started, the rupture escape electron mitigation system 7 injects a large amount of argon (the gas volume is ten times that of background plasma) into the plasma core to dissipate the rupture escape electrons, and the task is completed.
In the plasma diagnosis data real-time acquisition system 1, the plasma fracture diagnosis resolution time is 0.1-1ms, the spatial resolution length of the section diagnosis data is 0.1-10cm, and the plasma fracture diagnosis data real-time acquisition system is used for acquiring diagnosis data of the system in real time, and comprises a soft X-ray array, a high-frequency magnetic measurement array, plasma radiation power, electron density section measurement, a plasma thermal radiation array and plasma energy storage.
In the intelligent early warning algorithm module 2 for plasma fracture, the success rate of the early warning for plasma fracture is higher than 95% through training of 100 times of plasma discharge data by the intelligent neural network early warning algorithm for plasma fracture.
In the above-described crack escape electron avoiding system 6, the magnetic island measurement accuracy of the magnetic fluid instability is less than 1cm; the magnetic fluid instability suppression time is less than 30ms; the rupture avoidance system reaction time is less than 1ms.
The plasma diagnosis data real-time acquisition system 1, the plasma rupture intelligent early warning algorithm module 2 and the central processing system 3 jointly realize the plasma rupture early warning,
wherein: the plasma diagnosis data real-time acquisition system 1 transmits measurement data for identifying the rupture to the intelligent early warning algorithm module 2 in real time, the intelligent early warning algorithm module 2 rapidly identifies and early warns the rupture of the plasma in real time, and then early warning information is sent to the central processing system 3.
Thereafter, plasma fracture control and mitigation is achieved by the central processing system 3, the fracture avoidance system 4, the thermal deposition corona current mitigation system 5, the fracture escape electron avoidance system 6, the fracture escape electron mitigation system 7, and the plasma fracture control and mitigation termination system 8 together, as follows:
after the central processing system 3 receives the rupture early warning information, firstly, sending an opening instruction to the rupture avoidance system 4, and completing the task if the rupture avoidance is successfully realized; if the occurrence of cracking is not successfully prevented, the thermal deposition and corona current mitigation system 5 and the cracking escape electron avoidance system 6 are activated simultaneously;
the thermal deposition and corona current relieving system 5 relieves thermal deposition and corona current generated by cracking, the cracking escape electron avoiding system 6 avoids the generation of cracking escape electrons, and if the situation that the generation of cracking escape electrons is avoided is successfully realized, the task is completed; if the generation of the cracking escape electrons is not successfully avoided, the cracking escape electron mitigation system 7 is started to mitigate the cracking escape electrons, and the task is completed.
The thermal deposition and corona current mitigation system 5, the rupture escape electron mitigation system 7, and the plasma rupture control and mitigation termination system 8 together achieve mitigation of plasma rupture escape electrons by the following process:
when the occurrence of plasma rupture is not realized, the thermal deposition and corona current relieving system 5 receives a starting instruction, and a large amount of inert gas is injected into the plasma to relieve the ruptured thermal deposition and corona current.
When the generation of the burst escape electrons is not realized, the burst escape electron mitigation system 7 receives a start instruction, injects a large amount of argon gas into the plasma core, and mitigates the burst escape electrons.
After the completion of the burst escape electron mitigation system 7, a completed instruction is issued to the plasma burst control and mitigation termination system 8, and the plasma burst control and mitigation termination system 8 terminates all tasks of the present plasma burst real-time control and mitigation and issues a completed instruction to the central processing system 3. The whole plasma fracture control and relief system enters a real-time standby state again, and waits for the next plasma fracture.
During plasma fracture mitigation, the reaction time of the thermal deposition with the corona current mitigation system 5 and the fracture escape electron mitigation system 7 is less than 1ms; the impurity injection quantity is controllable, and the number of injected atoms is in the range of 10 21 -10 24 A plurality of; the speed of injecting impurities is controllable, and the range of the speed is 300-1000m/s; the pulse width of the impurity injection is controllable, and the range of the pulse width is 1-100ms; the impurity injection frequency is controllable, and the range is 1-100Hz.
Amplitude of magnetic field disturbance in the rupture escape electron avoidance system 6Greater than 10 -3 T is a T; magnetic disturbance penetration depth q=1; the burst escape electrons avoid a system reaction time of less than 1ms.
Claims (13)
1. Tokamak plasma rupture real-time control and relief system, its characterized in that: the plasma diagnosis system comprises a plasma diagnosis data real-time acquisition system (1), a plasma fracture intelligent early warning algorithm module (2), a central processing system (3), a fracture avoiding system (4), a thermal deposition and corona current relieving system (5), a fracture escape electron avoiding system (6), a fracture escape electron relieving system (7) and a plasma fracture control and relieving termination system (8);
the plasma diagnosis data real-time acquisition system (1) transmits the high-space-time resolution measurement data related to plasma fracture to the intelligent early warning algorithm module (2);
the intelligent early warning algorithm module (2) for plasma fracture carries out rapid real-time identification and early warning on plasma fracture and transmits early warning information to the central processing system (3);
the central processing system (3) sends a starting instruction to the rupture avoidance system (4);
the rupture avoidance system (4) successfully prevents the rupture, and sends an end task instruction to the plasma rupture control and relief termination system (8);
the rupture avoidance system (4) does not successfully prevent rupture, and then sends a start instruction to the thermal deposition and corona current mitigation system (5) and the rupture escape electronic avoidance system (6) at the same time;
the thermal deposition and corona current mitigation system (5) achieves mitigation of thermal deposition and corona currents generated during plasma rupture;
the rupture escape electron avoidance system (6) consumes escape "seed" electrons, wherein:
if the avoidance of the broken escape electrons is successfully realized, sending an end task instruction to a plasma breakage control and relief termination system (8);
if the generation of the cracking escape electrons is not successfully prevented, starting a cracking escape electron mitigation system (7);
the cracking escape electron relieving system (7) dissipates the cracking escape electrons until the cracking escape electron avoidance is successfully realized, and then sends an ending task instruction to the plasma cracking control and relieving termination system (8).
2. The tokamak plasma break real time control and mitigation system of claim 1, wherein: the thermal deposition and corona current relieving system (5) injects inert gas into the plasma, wherein the volume of the injected gas is ten times that of background plasma, and the thermal deposition and corona current generated during the plasma rupture is relieved.
3. The tokamak plasma break real time control and mitigation system of claim 1, wherein: the rupture escape electron avoidance system (6) consumes escaping "seed" electrons when the plasma core produces a strong magnetic disturbance.
4. The tokamak plasma break real time control and mitigation system of claim 3, wherein: the strong magnetic disturbance is B ̃/B > 10 -3 B ̃ is the magnetic field disturbance amplitude, and B is the plasma circumferential magnetic field strength.
5. The tokamak plasma break real time control and mitigation system of claim 1, wherein: the rupture escape electron mitigation system (7) injects argon into the plasma core to dissipate the rupture escape electrons.
6. The tokamak plasma break real time control and mitigation system of claim 5, wherein: the injection volume of the argon gas is ten times that of background plasma.
7. The tokamak plasma break real time control and mitigation system of claim 1, wherein: in the plasma diagnosis data real-time acquisition system (1), the plasma fracture diagnosis resolution time is 0.1-1ms, and the spatial resolution length of the section diagnosis data reaches 0.1-10cm.
8. The tokamak plasma break real time control and mitigation system of claim 1, wherein: in the intelligent early warning algorithm module (2) for plasma fracture, a neural network algorithm is utilized to train plasma discharge data.
9. The tokamak plasma break real time control and mitigation system of claim 1, wherein: in the rupture escape electron avoiding system (6), the measurement precision of the magnetic islands of the magnetic fluid instability is less than 1cm; the magnetic fluid instability suppression time is less than 30ms; the rupture avoidance system reaction time is less than 1ms.
10. A method for real-time control and mitigation of tokamak plasma break, characterized in that it is based on the tokamak plasma break real-time control and mitigation system according to claim 1, the method comprising the steps of:
step 1), a plasma diagnosis data real-time acquisition system (1) transmits high-space-time resolution measurement data related to plasma fracture to a plasma fracture intelligent early warning algorithm module (2);
step 2), the intelligent early warning algorithm module (2) for plasma fracture carries out rapid real-time identification and early warning on the plasma fracture and transmits early warning information to the central processing system (3);
step 3), according to the rapid identification and early warning information of the plasma fracture sent by the intelligent early warning algorithm module (2), the central processing system (3) sends a starting instruction to the fracture avoiding system (4): if the fracture avoidance is successfully prevented, completing the task, and if the fracture is not successfully prevented, starting a thermal deposition and corona current relieving system (5) and a fracture escape electron avoiding system (6) at the same time;
step 4), the thermal deposition and corona current relieving system (5) injects inert gas into the plasma, wherein the volume of the injected gas is ten times that of background plasma, so that the thermal deposition and corona current generated during the plasma rupture is relieved;
step 5), when the strong magnetic disturbance is generated on the plasma core, the cracking escape electron avoiding system (6) consumes escaping seed electrons, if the cracking escape electron avoiding is successfully realized, the task is completed, if the cracking escape electron is not successfully prevented, the cracking escape electron relieving system (7) is started;
step 6), after the fracture escape electron mitigation system (7) is started, a large amount of argon is injected into the plasma core part by the fracture escape electron mitigation system (7), and the fracture escape electrons are dissipated, so that the task is completed.
11. The method for real-time control and mitigation of plasma cracking of tokamak in accordance with claim 10, wherein: the plasma diagnosis data real-time acquisition system (1), the plasma fracture intelligent early warning algorithm module (2) and the central processing system (3) jointly realize plasma fracture early warning, the plasma diagnosis data real-time acquisition system (1) transmits measurement data for identifying fracture to the plasma fracture intelligent early warning algorithm module (2) in real time, the plasma fracture intelligent early warning algorithm module (2) rapidly identifies and early warns the plasma fracture in real time, and then early warning information is sent to the central processing system (3).
12. The method for real-time control and mitigation of plasma cracking of tokamak in accordance with claim 11, wherein: the central processing system (3), the rupture avoidance system (4), the thermal deposition and corona current alleviation system (5), the rupture escape electron avoidance system (6), the rupture escape electron alleviation system (7) and the plasma rupture control and alleviation termination system (8) jointly realize the control and alleviation of plasma rupture, and the process is as follows: after the central processing system (3) receives the rupture early warning information, firstly, sending an opening instruction to the rupture avoidance system (4), and if the rupture avoidance is successfully realized, completing the task; if the occurrence of cracking is not successfully prevented, a thermal deposition and corona current mitigation system (5) and a cracking escape electron avoidance system (6) are activated simultaneously.
13. The method for real-time control and mitigation of plasma cracking of tokamak in accordance with claim 12, wherein: the thermal deposition and corona current relieving system (5), the cracking escape electron relieving system (7) and the plasma cracking control and relieving termination system (8) jointly realize the relieving effect of the plasma cracking escape electrons, and the process is as follows:
when the occurrence of plasma rupture is not realized, the thermal deposition and corona current relieving system (5) receives a starting instruction, and a large amount of inert gas is injected into the plasma to relieve the thermal deposition and corona current of the rupture;
when the generation of the cracking escape electrons is not realized, a cracking escape electron relieving system (7) receives a starting instruction, and a large amount of argon is injected into the plasma core to relieve the cracking escape electrons;
after the breaking escape electron relieving system (7) is completed, a completed instruction is sent to the plasma breaking control and relieving termination system (8), and the plasma breaking control and relieving termination system (8) terminates all tasks of the plasma breaking real-time control and relieving and sends the completed instruction to the central processing system (3).
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Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN101533680A (en) * | 2009-04-20 | 2009-09-16 | 中国科学院等离子体物理研究所 | Method for removing hydrogen detained on first wall in nuclear fusion device by direct current glow oxygen plasma |
CN103822532A (en) * | 2014-02-26 | 2014-05-28 | 中国科学院等离子体物理研究所 | Multi-lithium-ball-projectile accurate automatic supply system special for plasma fracturing protecting |
CN105587912A (en) * | 2014-10-20 | 2016-05-18 | 核工业西南物理研究院 | Rapid charging valve of special-purpose double-eddy-current coil used for plasma fracture protection |
CN108172308A (en) * | 2018-01-10 | 2018-06-15 | 成都大学 | The method that plasma inhibition escape electric current is penetrated based on RMP |
CN108288509A (en) * | 2018-01-10 | 2018-07-17 | 成都大学 | The method and device that enhancing magnetic disturbance inhibits escape electric current is injected based on gas |
WO2021122588A1 (en) * | 2019-12-17 | 2021-06-24 | Tokamak Energy Ltd | Inboard shaping using a modified solenoid |
-
2021
- 2021-12-17 CN CN202111551974.5A patent/CN114360747B/en active Active
Patent Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN101533680A (en) * | 2009-04-20 | 2009-09-16 | 中国科学院等离子体物理研究所 | Method for removing hydrogen detained on first wall in nuclear fusion device by direct current glow oxygen plasma |
CN103822532A (en) * | 2014-02-26 | 2014-05-28 | 中国科学院等离子体物理研究所 | Multi-lithium-ball-projectile accurate automatic supply system special for plasma fracturing protecting |
CN105587912A (en) * | 2014-10-20 | 2016-05-18 | 核工业西南物理研究院 | Rapid charging valve of special-purpose double-eddy-current coil used for plasma fracture protection |
CN108172308A (en) * | 2018-01-10 | 2018-06-15 | 成都大学 | The method that plasma inhibition escape electric current is penetrated based on RMP |
CN108288509A (en) * | 2018-01-10 | 2018-07-17 | 成都大学 | The method and device that enhancing magnetic disturbance inhibits escape electric current is injected based on gas |
WO2021122588A1 (en) * | 2019-12-17 | 2021-06-24 | Tokamak Energy Ltd | Inboard shaping using a modified solenoid |
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