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CN-114974797-B - Superconducting magnet and simulation device for plasma restraint

CN114974797BCN 114974797 BCN114974797 BCN 114974797BCN-114974797-B

Abstract

The invention discloses a superconducting magnet and a simulation device for plasma restraint, wherein the superconducting magnet comprises a framework, a superconducting coil is arranged on the framework, the superconducting coil comprises a middle coil and end coils, a cooling medium tank, a cold screen and a vacuum dewar inner cylinder body are sequentially arranged outside the framework, a superconducting power supply comprises a first superconducting power supply and a second superconducting power supply, the first superconducting power supply supplies power to the middle coil and the end coils at the same time, the second superconducting power supply supplies power to the end coils when needed, a protection diode is connected in parallel with two ends of the middle coil and two ends of the end coils, a radial hoisting rod is arranged outside the framework, and an axial hoisting rod is parallel with the axial direction of the framework. The invention not only realizes adjustable magnetic field uniformity, but also can effectively ensure the safety of the superconducting magnet when the magnet is out of time, and simultaneously reduces the influence of heat leakage under the condition of meeting the hoisting and transportation protection requirements.

Inventors

  • LIU WEI
  • YANG ZHANFENG
  • FENG YONG
  • LIU XIANGHONG
  • ZHANG PINGXIANG
  • MA PENG
  • LI CHAO
  • LI MENG
  • ZHANG WENTAO
  • HAN ZHICHEN
  • GE ZHENGFU
  • LAN XIANHUI
  • ZHOU TAO

Assignees

  • 西安聚能超导磁体科技有限公司

Dates

Publication Date
20260505
Application Date
20220628

Claims (10)

  1. 1. A superconducting magnet for plasma confinement, comprising: The superconducting coil (102) comprises a middle coil and end coils, wherein the two end coils are respectively arranged at two end edges of the framework (103), the middle coil is arranged between the two end coils, the winding thickness of the end coils on the framework (103) is larger than that of the middle coil on the framework (103), a cooling medium groove (104), a cold screen (105) and a vacuum dewar inner cylinder (106) are sequentially arranged outside the framework (103), the cooling medium groove (104), the cold screen (105) and the vacuum dewar inner cylinder (106) are of circular-ring columnar structures, and the diameters of the framework (103), the cooling medium groove (104), the cold screen (105) and the vacuum dewar inner cylinder (106) are sequentially increased to enable the diameters of the cooling medium groove (104) and the cooling medium groove to be sequentially nested, and the cooling medium groove (104) is used for containing liquid cooling medium so that the superconducting coils (102) are at the critical temperature or lower; A superconducting power supply comprising a first superconducting power supply (111) and a second superconducting power supply (112), the first superconducting power supply (111) supplying power to the middle coil and end coils simultaneously, the second superconducting power supply (112) supplying power to the end coils when required; A protection diode (113) connected in parallel with two ends of the middle coil and two ends of the end coil, wherein the protection diode (113) is composed of two anti-parallel diodes; the radial hoisting rod (109) is arranged outside the framework (103), and the radial hoisting rod (109) penetrates through the cooling medium groove (104), the cold screen (105) and the vacuum dewar inner barrel (106) and extends out of the vacuum dewar inner barrel (106); and the axial lifting rod (108) is parallel to the axial direction of the framework (103), and the axial lifting rod (108) passes through the cooling medium groove (104), the cold screen (105) and the vacuum dewar inner barrel (106) and extends out of the vacuum dewar inner barrel (106).
  2. 2. A superconducting magnet for plasma confinement according to claim 1, wherein a refrigerator (101) is provided on the outer side of the vacuum dewar inner cylinder (106), the cold head of the refrigerator (101) being in contact with the superconducting coil (102) through a condenser (101-C).
  3. 3. A superconducting magnet for plasma confinement according to claim 2, characterized in that the cold head of the refrigerator (101) comprises a primary cold head (101-a) and a secondary cold head (101-B), the secondary cold head (101-B) being in contact with the superconducting coil (102) through the condenser (101-C), the primary cold head (101-a) being in contact with the cold screen (105).
  4. 4. A superconducting magnet for plasma confinement according to claim 3, wherein the cold shield (105) comprises: a cylinder (105-B); The protruding structure (105-A) is arranged on the outer side face of the cylinder body (105-B), the protruding structure (105-A) is provided with a connecting hole (105-D), the primary cold head (101-A) is inserted into the connecting hole (105-D) and is in contact with the protruding structure (105-A), and the primary cold head (101-A) also passes through the connecting hole (105-D) to be connected with the secondary cold head (101-B).
  5. 5. A superconducting magnet for plasma confinement according to claim 4, wherein the cylinder (105-B) is provided with a plurality of heat conducting slits (105-E) therethrough.
  6. 6. A superconducting magnet for plasma confinement according to claim 1, wherein the first superconducting power supply (111) and the second superconducting power supply (112) are each electrically connected to the superconducting coil (102) by a circuit breaker (114).
  7. 7. A superconducting magnet for plasma confinement according to claim 1, wherein the superconducting coil (102) is electrically connected to a current lead (107), the current lead (107) being electrically connected to the superconducting power supply after passing through the cooling medium tank (104), cold shield (105) and vacuum dewar inner cylinder (106).
  8. 8. A superconducting magnet for plasma confinement according to claim 1, wherein the vacuum dewar inner cylinder (106) is provided with a support base (110) on its bottom side.
  9. 9. A simulation device for plasma confinement, characterized by comprising an ion source (2), a test sample (3) and a superconducting magnet (1) for plasma confinement according to any of claims 1-8, the ion source (2) being arranged directly opposite to the test sample (3), the ion source (2) and the test sample (3) being arranged inside the superconducting magnet (1) in the axial direction of the superconducting magnet (1).
  10. 10. A simulation device for plasma confinement according to claim 9, characterized in that the inside of the superconducting magnet (1) is provided with a vacuum cavity in which the ion source (2) and the test sample (3) are arranged in the axial direction.

Description

Superconducting magnet and simulation device for plasma restraint Technical Field The invention relates to the technical field of superconducting equipment, in particular to a superconducting magnet for plasma restraint and a simulation device. Background Nuclear fusion research is a major international collaboration program developed by the world technology community today to solve the energy problem in the future of humans. Unlike non-renewable energy and conventional clean energy, fusion energy has the advantages of infinite resources, no environmental pollution, no generation of high-radioactivity nuclear waste and the like, is one of the dominant forms of human future energy, and is one of the important ways which are recognized at present and can finally solve the energy problems and the environmental problems of the human society and promote the sustainable development of the human society. The international thermonuclear fusion experimental reactor (ITER) project is one of the most profound international scientific research projects of the current global standard, and costs 50 hundred million dollars for construction for about 10 years. The ITER device is a superconducting tokamak capable of producing large-scale nuclear fusion reactions, commonly known as "artificial sun". The ITER program is an essential step in achieving fusion energy commercialization, with the goal of verifying and making use of the scientific and technical feasibility of fusion energy. The ITER plan integrates the main scientific and technical achievements of the current international controlled magneto-restrictive nuclear fusion research, has reliable scientific basis and has solid technical foundation. As a core component inside a magneto-restrictive nuclear fusion reaction chamber, a divertor (Divertor) is part of a toroidal fusion device (e.g., tokamak) that is used to divert charged particles within the outer shell of a discharge into a separate chamber where they bombard a baffle plate, turning into neutral particles that are pumped away. In this way, the bombardment of the main discharge chamber wall by energetic particles in the outer envelope is avoided, and thus the release of secondary particles from the chamber wall, which can cool the discharge, is avoided. Therefore, research on the relevant performance of the filter under the action of plasma is the key for successfully designing and manufacturing commercial divertors. However, a large-scale experimental platform needs to be built for researching the material service performance of the divertor in the plasma environment, and plasma related parameters in the real nuclear fusion environment are simulated. The core component of the experimental platform, namely the large superconducting strong magnet device, has high design technical difficulty, high processing and manufacturing difficulty, high risk and other reasons, so that related basic research and technical accumulation are lacking in China. In addition, even if the existing magnet device can complete the simulation work, the problems are that (1) the uniformity of a magnetic field cannot be adjusted and the constraint and control requirements of plasmas with different working mediums cannot be met, (2) the superconducting magnet stores large energy, a large amount of energy is released in a short time after the magnet is quenched, so that the magnet is burnt out, and (3) the adopted hoisting structure cannot meet the requirements of stress, transportation protection and the like under the condition of small heat leakage. Disclosure of Invention The embodiment of the invention provides a superconducting magnet and a simulation device for plasma restraint, which are used for solving the problems that in the prior art, the magnetic field uniformity of a magnet device cannot be adjusted, the magnet is burnt out after the magnet is quenched, a hoisting structure cannot be considered less heat leakage, and the stress and transportation protection requirements are met. In one aspect, embodiments of the present invention provide a superconducting magnet for plasma confinement, comprising: The superconducting coil comprises a middle coil and end coils, wherein the two end coils are respectively arranged at the edges of two ends of the framework, and the middle coil is arranged between the two end coils; the superconducting power supply comprises a first superconducting power supply and a second superconducting power supply, wherein the first superconducting power supply supplies power to the middle coil and the end coils simultaneously, and the second superconducting power supply supplies power to the end coils when needed; the protection diode is connected in parallel with two ends of the middle coil and two ends of the end coil; The radial hoisting rod is arranged at the outer side of the framework, penetrates through the cooling medium groove, the cold screen and the vacuum dewar inner cylinder body and extends ou