CN2563708Y - Controllable nuclear fusion power device - Google Patents
Controllable nuclear fusion power device Download PDFInfo
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- CN2563708Y CN2563708Y CN01273905U CN01273905U CN2563708Y CN 2563708 Y CN2563708 Y CN 2563708Y CN 01273905 U CN01273905 U CN 01273905U CN 01273905 U CN01273905 U CN 01273905U CN 2563708 Y CN2563708 Y CN 2563708Y
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- Y—GENERAL 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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
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Abstract
Disclosed is a power plant for producing controllable nuclear fusion energy, which mainly adopts hydrogen isotopic deuterium and deuterium as fuel. The device adopts the ion implantation, laser and neutron for ignition. The high pressure deuterium gas and deuterium gas enter a vacuum chamber after the ionization by a plasma nozzle and are converged into a fusion nuclear reaction zone of a fusion reactor after the acceleration, and a high power laser module and a strong neutron source assembly which encircle an ion implanter heat and pressurize the ion for realizing the ignition and maintaining the combustion. The fusion reactor is a container having three layers of spherical shells, the inner shell adopts a compound graphite layer to absorb light and thermal radiation and reflect neutron, and the outer layers of the graphite layer are a sodium metal heat carrier container and a thermal insulation water hull formed by a heat resisting steel mantle and a shell. The liquid sodium metal used as a heat carrier is input into a heat exchanger to produce superheating steam for driving a generating set of a steam turbine to generate electricity. The power plant is used for providing low-cost energy sources.
Description
Belongs to the technical field of: the utility model relates to a power device for generating controllable nuclear fusion energy, which mainly adopts deuterium and tritium isotopes of hydrogen as fuel.
Background art: currently, controllable nuclear fusion is known to use magnetic confinement (TOKAMAK tomak) and inertial confinement devices. These devices are only experimental devices as they have not fully solved the problem of achieving controlled nuclear fusion ignition and self-sustaining combustion conditions.
The purpose of the utility model is that: the utility model aims at providing a produce the power device of controllable nuclear fusion energy. The technical scheme is as follows: the purpose of the utility model is realized like this: high pressure deuterium gas1 2H (pressure greater than 50MPa) (50% -100%) and tritium gas1 3H (0% -50%) is ionized by electric arc at high temperature through a plasma nozzle, enters a vacuum chamber of an ion injector, is primarily accelerated, de-elected, accelerated and pumped out of non-ionized gas through an electric field (high-voltage electrode), and is diffused, accelerated and focused in a fusion nuclear reaction region of a fusion reactor under the action of a positive ion diffusion electromagnet, an accelerating electromagnet, a focusing electromagnet and a deflection and focusing fine adjustment electromagnet sleeved on the vacuum chamber. A high-power laser group (oxygen-iodine chemical laser or crossflow CO2 carbon dioxide gas laser) surrounding the ion injector focuses laser beams on a fusion nuclear reaction area of a fusion reactor through a lens to heat and pressurize ions. A group of strong neutron sources arranged outside the ion injector focuses neutron beams on a fusion nuclear reaction region of the fusion reactor from the (spherical or elliptical) inner wall of the neutron source. The nuclear fusion nuclear reaction is ignited under the action of the laser beam and the neutron beam. The fusion reactor is a three-layer ellipsoid or spherical shell container, the inner shell is a metal sodium (potassium) heat carrier container consisting of a composite graphite layer for absorbing light and heat radiation and reflecting neutrons, and the graphite layer is a heat-resistant steel shell, a heat-insulating water shell and an outer shell. The high-temperature liquid metal sodium is input into the heat exchanger to generate superheated steam to drive the steam turbine generator set to generate power, and the power range is more than 10000 kilowatts. The device adopts ion implantation, laser and neutron ignition, and is based on the following nuclear reaction of hydrogen isotopes:
Description of the drawings: the invention will be further described with reference to the following figures and examples: fig. 1 is a structural view of a controllable nuclear fusion reactor of the present invention. Fig. 2 is a diagram of the structure of the laser system (oxy-iodine chemical laser) of the present invention. Fig. 3 is a view of the structure of the laser system according to the present invention. Fig. 4 is a construction view of a fusion reactor of the present invention. Figure 5 is a block diagram of an ion implanter according to the present invention. Fig. 6 is an enlarged view of the ion implanter of the present invention at section I. FIG. 7 is a structural diagram of the neutron source of the present invention. Fig. 8 is a configuration diagram of an embodiment of the present invention. Fig. 9 is a construction diagram of a controllable nuclear fusion reactor using heavy ion implantation according to the present invention. Figure 10 is a block diagram of a heavy ion implanter according to the present invention.
In the figure: 1. fusion reactor 2, ion injector 3, neutron source 4, laser system 5, high temperature heat exchange medium delivery pump 6, fusion reactor shell cooling and preheater 7, high pressure heat exchanger 8, waste heat exchanger 9, water tank and cooling water heat exchanger 10, turbo generator set 11, protective shell 12, fuel (deuterium gas, tritium gas) injector 13, high temperature heat exchange medium pipeline 14, ion injector vacuum pump 15, fusion reactor mechanical vacuum pump 16, ion injector power supply 17, isotope and gas separator 18, fusion reactor shell cooling pipeline 19, superheated steam pipeline 20, cooling water pump 21, power output wiring terminal 22, hot water supply outlet 23, cold water inlet 24, control chamber 25, heavy ion injector101. Inner shell 102, metal sodium cavity 103, water cavity 104, insulating water shell 106, outer shell 107, cooling water inlet 108, thermal medium inlet 109, machine manhole 110, laser hole 111, neutron source hole 112, ion injector hole 113, operation interface 114, fusion reactor vacuum pump interface 115, thermal medium outlet 116, cooling water outlet 117, protective layer 118, and thermal insulation layer119. The plasma processing system comprises a thickened reflecting layer 120, an observationhole 121, an ion stabilizing pipe 122, a reflecting cover 203, a positive ion diffusion electromagnet 204, an accelerating electromagnet 205, a focusing electromagnet 206, a focusing fine adjustment electromagnet 207, a deflecting electromagnet 208, an ion injector vacuum chamber 211, a plasma nozzle 212, a primary accelerating electrode 213, an electron removing electrode 214, an accelerating electrode 215, a vacuum pump interface 216, a cooling water interface 217, a plasma generator 220, a junction box and a cable 224, an ion injector cooling water system 225, a cooling water tank 301, an ellipsoidal focal point neutron emission-reflection composite layer 302, an ellipsoidal neutron emission-reflection composite layer 303, a radiation protection valve 304, a protection shell 400, a laser 401, a voltage stabilizing oxygen generator 402, an oxygen input pipe collar 403, an iodine input collar 404, an exhaust collar 405, an iodine atom generator 406, an exhaust pump 407, an iodine recovery system 408, a low-temperature pump purification system 409, a low temperature pump The refrigerating unit 410, chlorine tank 411, KOH tank 412, H2O2Tank 413, reaction wastewater tank 414, reaction wastewater pipeline 415, chlorine pipeline 416, KOH + H2O2 Pipeline 417, liquid chlorine tank 1210, fuel injection pipeline 1221, fuel injection pump 1222, fuel tank 1901, superheated vapor outlet 1902, condensed water inlet 2526, uranium vapor generator 2527, uranium separation plant
In fig. 1 (see fig. 2 and 4), two sets of ion injectors (2) are horizontally connected to the left and right sides of the fusion reactor (1) through ion injection holes (112), respectively, for injecting high energy ions into the fusion reactor. The group of neutron sources (3) is arranged outside the ion injector (2) in a surrounding mode and is connected with the fusion reactor through a neutron source hole (111). The group of lasers (4) is arranged around the outside of the group of neutron sources (3) and is connected with the fusion reactor through a laser hole (110). The laser (4) group is arranged on the left side and the right side of the fusion reactor (1) through an integral structure formed by an oxygen input pipe loop (402), an iodine input loop (403) and an exhaust loop (404). The two sets of fusion reactor mechanical vacuum pumps (15) and the isotope and gas separator (17) are connected to the fusion reactor (1) through a fusion reactor vacuum pump interface (114) and used for keeping the vacuum degree in the fusion reactor and separating the isotope. Heat exchange medium (Metal)Sodium) is input into a metal sodium cavity (102) through a heat medium inlet (108) at the bottom of the fusion reactor by a high-temperature heat exchange medium delivery pump (5) for heat exchange, and then enters a high-pressure heat exchanger (7) through a high-temperature heat exchange medium pipeline (13) by a heat medium outlet (115) at the top of the reactor for producing superheated steam. The shell cooling and preheating device (6) of the fusion reactor and the high-pressure heat exchanger (7) of the fusion reactor are arranged on a partition wall in a separated mode through a partition wall of a protective shell (11). In FIG. 2, chlorine tank (410), KOH tank (411), H2O2The tank (412), the reaction waste water tank (413) and the liquid chlorine tank (417) are arranged on the same support, and chlorine and KOH + H2O2The liquid passes through a chlorine pipeline (415) and KOH + H2O2Line (416) feeds into the steady-pressure oxygen generator (401) and the reaction wastewater flows back to the reaction wastewater tank (413) through the reaction wastewater line (414). The pressure stable oxygen generated in the pressure stable oxygen generator (401) and the iodine atoms generated in the iodine atom generator (405) are mixed in the laser nozzle at high speed through theoxygen input pipe loop (402) and the iodine input loop (403) and are subjected to resonance transfer energy transfer to generate laser. The steady-state oxygen generators (401) and the iodine atom generators (405) are arranged outside the oxygen input pipe ring pipe (402) in groups. In fig. 4, the fusion reactor is a three-layer spherical shell vacuum vessel, which is composed of an inner shell (101), a heat-preservation water shell (104) and an outer shell (106). The device comprises a machine manhole (109), a laser hole (110), a neutron source hole (111), an ion injection hole (112), an operation interface (113) and a fusion reactor vacuum pump interface (114), wherein the machine manhole, the laser hole (110), the neutron source hole (111), the ion reactor vacuum pump interface and the fusion reactor vacuum pump interface penetrate through an inner shell (101), a heat-preservation water shell (104) and an outer shell (106) through connecting pipes and are introduced into a. The heat medium inlet (108) and the heat medium outlet (115) are communicated with the sodium metal cavity (102). The cooling water inlet (107) and the cooling water outlet (116) are communicated with the water cavity (103). In fig. 5, a positive ion diffusion electromagnet (203), an acceleration electromagnet (204), a focusing electromagnet (205), a focusing fine adjustment electromagnet (206), and a deflection electromagnet (207) are provided outside the vacuum chamber (208) of the ion implanter.In fig. 10, a uranium vapor generator (2526) is placed in front of a plasma generator, a uranium separation device (2527) is used for separating non-ionized uranium, and a positive ion diffusion electromagnet (203), an acceleration electromagnet (204), a focusing electromagnet (205), a focusing fine adjustment electromagnet (206), a deflection electromagnet (207) are sleeved outside an ion injector vacuum chamber (208). Realize the practicalityThe novel best mode is as follows: in the embodiment of fig. 1, two sets of ion injectors (2), neutron sources (3), lasers are arranged on two sides of a fusion reactor (1), hydrogen isotopes deuterium and tritium are used as fuels, and the fuels (deuterium gas and tritium gas) are injected into the ion injectors (2) through the fuel injectors (12), are accelerated through plasma generation and accelerators, are injected into the fusion reactor (1) through positive ion diffusion electromagnets (203), acceleration electromagnets (204), focusing electromagnets (205), deflection electromagnets (207) and focusing fine adjustment electromagnets (206). A group of high-power lasers (4) (8-12O-I oxygen-iodine chemical lasers or cross-flow CO2 carbon dioxide gas lasers on each side) surrounding the ion injector (2) focus laser beams on a fusion nuclear reaction area (fusion reactor center) of the fusion reactor through lenses to heat and pressurize ions. The group of strong neutron sources (3) arranged outside the ion injector (2) focuses neutron beams on the fusion nuclear reaction area of the fusion reactor through the inner wall (spherical or elliptical) of the neutron source. The fusion reactor (1) is a three-layer spherical shell vacuum container and consists of an inner shell (101), a heat-preservation water shell (104) and an outer shell (106), wherein the inner shell (101) is a composite graphite layer and absorbs light and heat radiation and reflects neutrons, and a metal sodium (potassium) heat carrier is filled between the inner shell (101) and the heat-preservation water shell (104) (a metal sodium cavity (102)) and exchanges heat with a high-pressure heat exchanger (7) through circulation of a high-temperature heat exchange medium delivery pump (5). The heat preservation water passes through the water cavity (103) of the fusion reactor and the preheater (6) and then reaches the water tank and the cooling water heat exchanger (9). The high-pressure heat exchanger (7) generates superheated steam and outputs the superheated steam through a superheated steam outlet (1901).
In the embodiment of fig. 8, superheated steam generated by the high-pressure heat exchanger (7) in the embodiment of fig. 1 drives a turbo generator set (10) to generate power, and a complete controllable nuclear fusion power device is formed by the waste heat exchanger (8), a hot water supply outlet (22), a cold water inlet (23) and a control room (24) through a water tank and a power output connection terminal (21) of a cooling water heat exchanger (9). In the embodiment of fig. 9, one of the two ion implanters of the embodiment of fig. 1 is designed as a heavy ion injector (25) to inject uranium ions to assist in igniting the nuclear fusion reaction. The heavy ion injector (25) is a fuel (tritium gas ) injector (12) designed as a uranium steam generator (2526) for ionizing and accelerating uranium steam for injection into the fusion reactor.
Claims (3)
1. A power plant for generating controllable nuclear fusion energy is characterized in that: two sets of ion injectors, neutron sources and lasers are arranged on two sides of the fusion reactor; the fuel injector is arranged in front of the ion injector, and the positive ion diffusion electromagnet, the accelerating electromagnet, the focusing fine adjustment electromagnet and the deflection electromagnet are sleeved outside the vacuum chamber of the ion injector; the high-power laser group surrounding the ion injector is characterized in that a chlorine tank, a potassium hydroxide tank, a hydrogen peroxide tank, a reaction wastewater tank and a liquid chlorine tank are arranged on the same support and are connected to a pressure-stable state oxygen generator through a chlorine pipe line, a potassium hydroxide pipe line and a hydrogen peroxide pipe line, the reaction wastewater pipe line is connected with the reaction wastewater tank, the pressure-stable state oxygen generator is connected with an oxygen input pipe ring pipe, an iodine atom generator is connected with an iodine input ring pipe, and the pressure-stable state oxygen generator and the iodine atom generator are arranged outside the oxygen input ring pipe in groups; the strong neutron source group is arranged outside the ion implanter; the fusion reactor is a three-layer spherical shell vacuum container and consists of an inner shell, a heat-preservation water shell and an outer shell, wherein the inner shell and the heat-preservation water shell are connected with a high-temperature heat exchange medium delivery pump and a high-pressure heat exchanger through pipelines, the heat-preservation water shell and the outer shell are connected with a preheater, a water tank and a cooling water heat exchanger through pipelines, and the high-pressure heat exchanger is connected with a hot steam outlet through a pipeline.
2. A controllable nuclear fusion energy power plant as in claim 1, and further comprising: the high-pressure heat exchanger is connected with the turbo generator set through a pipeline and is connected with the waste heat exchanger, the water tank, the cooling water heat exchanger, the electric power output connection terminal, the hot water supply outlet, the cold water inlet and the control room.
3. A controllable nuclear fusion energy power plant as in claim 1, and further comprising: one of the two sets of ion implanters is designed as a heavy ion implanter; the heavy ion injector is characterized in that a uranium steam generator is arranged in front of an ion generator, and a positive ion diffusion electromagnet, an accelerating electromagnet, a focusing fine adjustment electromagnet, a deflection electromagnet sleeve and the outside of a vacuum chamber of the ion injector are arranged.
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CN01273905U CN2563708Y (en) | 2001-11-06 | 2001-11-06 | Controllable nuclear fusion power device |
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CN01273905U CN2563708Y (en) | 2001-11-06 | 2001-11-06 | Controllable nuclear fusion power device |
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CN01273905U Expired - Fee Related CN2563708Y (en) | 2001-11-06 | 2001-11-06 | Controllable nuclear fusion power device |
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Cited By (7)
Publication number | Priority date | Publication date | Assignee | Title |
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CN100351951C (en) * | 2005-04-11 | 2007-11-28 | 中国科学院等离子体物理研究所 | Mode for inpouring fuel into future tokamak type thermonuclear reactor power station |
WO2008128422A1 (en) * | 2007-04-18 | 2008-10-30 | Jiubin Chen | A nuclear reactor |
CN101645562B (en) * | 2009-09-10 | 2011-08-17 | 中国科学院等离子体物理研究所 | Multipurpose connector of remote transportation facility of nuclear fusion experimental reactor |
CN103489487A (en) * | 2013-09-11 | 2014-01-01 | 曾泓瑞 | Pulse discharging operating nuclear fusion reaction method and reaction device of pulse discharging operating nuclear fusion reaction |
CN103608868A (en) * | 2011-06-10 | 2014-02-26 | 曾宪俊 | Continuous fusion due to energy concentration through focusing of converging fuel particle beams |
CN106981317A (en) * | 2017-05-22 | 2017-07-25 | 中国工程物理研究院流体物理研究所 | Magnetized plasma fusion igniter and its local quick acceleration heating ignition method |
CN109857179A (en) * | 2019-03-22 | 2019-06-07 | 中国原子能科学研究院 | Control system for Electromagnetic isotope separator cooling system |
-
2001
- 2001-11-06 CN CN01273905U patent/CN2563708Y/en not_active Expired - Fee Related
Cited By (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN100351951C (en) * | 2005-04-11 | 2007-11-28 | 中国科学院等离子体物理研究所 | Mode for inpouring fuel into future tokamak type thermonuclear reactor power station |
WO2008128422A1 (en) * | 2007-04-18 | 2008-10-30 | Jiubin Chen | A nuclear reactor |
CN101645562B (en) * | 2009-09-10 | 2011-08-17 | 中国科学院等离子体物理研究所 | Multipurpose connector of remote transportation facility of nuclear fusion experimental reactor |
CN103608868A (en) * | 2011-06-10 | 2014-02-26 | 曾宪俊 | Continuous fusion due to energy concentration through focusing of converging fuel particle beams |
CN103608868B (en) * | 2011-06-10 | 2017-06-06 | 曾宪俊 | By the continuation fusion produced in the fuel pellet beamlet enable quantity set for focusing on convergence |
US10643753B2 (en) | 2011-06-10 | 2020-05-05 | Xian-Jun Zheng | Hollow particle beam emitter |
CN103489487A (en) * | 2013-09-11 | 2014-01-01 | 曾泓瑞 | Pulse discharging operating nuclear fusion reaction method and reaction device of pulse discharging operating nuclear fusion reaction |
CN103489487B (en) * | 2013-09-11 | 2016-05-11 | 曾泓瑞 | Pulsed discharge operation nuclear fusion reaction device |
CN106981317A (en) * | 2017-05-22 | 2017-07-25 | 中国工程物理研究院流体物理研究所 | Magnetized plasma fusion igniter and its local quick acceleration heating ignition method |
CN109857179A (en) * | 2019-03-22 | 2019-06-07 | 中国原子能科学研究院 | Control system for Electromagnetic isotope separator cooling system |
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