CN106251912A - Self-loopa tritium containment system based on proton conductor ceramic membrane - Google Patents
Self-loopa tritium containment system based on proton conductor ceramic membrane Download PDFInfo
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- CN106251912A CN106251912A CN201610671119.0A CN201610671119A CN106251912A CN 106251912 A CN106251912 A CN 106251912A CN 201610671119 A CN201610671119 A CN 201610671119A CN 106251912 A CN106251912 A CN 106251912A
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- tritium
- hto
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- proton conductor
- ceramic membrane
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
- G21B1/15—Particle injectors for producing thermonuclear fusion reactions, e.g. pellet injectors
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21B—FUSION REACTORS
- G21B1/00—Thermonuclear fusion reactors
- G21B1/11—Details
- G21B1/19—Targets for producing thermonuclear fusion reactions, e.g. pellets for irradiation by laser or charged particle beams
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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
- Y02E30/10—Nuclear fusion reactors
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- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
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- High Energy & Nuclear Physics (AREA)
- Separation Using Semi-Permeable Membranes (AREA)
Abstract
The present invention discloses a kind of self-loopa tritium containment system based on proton conductor ceramic membrane, is primarily adapted for use in the tritium containment system in deuterium tritium fusion neutron generator.The present invention is using proton conductor ceramic membrane as the core component of tritium target, and wherein proton conductor ceramic membrane is made up of fine and close oxide ceramics solid electrolyte and two porous electrodes.Self-loopa process is: HTO is ionized as tritium ion by external power supply at anode, and tritium ion spreads in porous anode and passes through electrolyte to after negative electrode, is reduced to tritium atom simultaneously by the bombardment generation deuterium tritium fusion of deuterium line.And negative electrode has neither part nor lot in the tritium of fusion reaction and is oxidized to HTO by cleaning system, collection Posterior circle is back to anode and is continuing with.The tritium target operating temperature of this system can improve to 800 1000 DEG C, is simultaneously achieved recycling of tritium, greatly improves the utilization rate of tritium.
Description
Technical field
The present invention relates to the technical field of self-loopa tritium containment system, be specifically related to a kind of based on proton conductor ceramic membrane from
Circulation tritium containment system, is mainly used in the tritium containment system of deuterium tritium fusion neutron generator.
Background technology
Deuterium tritium fusion reaction 14.1MeV neutron generator, as a kind of important neutron source, can be measured in Nuclear Data, gather
Become the various aspects such as heap material radiation damage research, quasiconductor nuclear hardening, radioactive breeding, treatment of cancer.Tritium containment system is this
Plant the key technology of neutron generator.Currently used tritium target typically makes tritiated titanium target with the adsorptive gaseous tritium of titanium material.Used
Cheng Zhong, owing to being bombarded by deuterium ion stream, heat flow density is up to kW/cm2Magnitude, needs tritium target to have higher heat stability.And
There are problems in used tritiated titanium target: (1) is adsorbed the titanium tritide formed on titanium film by tritium, and its obvious decomposition temperature is 343
DEG C, when temperature reaches 343 DEG C, tritium therein starts to discharge in a large number.Cause tritium gas from target sheet to prevent temperature overheating
Release, it is generally recognized that temperature must be controlled below 200 DEG C.(2) target sheet production process must be entered with the container of high sealing
Row contains, and is otherwise difficult to protect gaseous state tritium；(3), when tritium target lost efficacy, the tritium of D-T reaction is wherein occurred almost can to ignore
Disregarding, the practical efficiency of the tritium in tritium target is less than 0.5%；(4) having neither part nor lot in the tritium of reaction, only 20% enters tritium cleaning system
System, remaining tritium of 80% still remains in tritium target and cannot utilize.Above reason causes tritiated titanium target expensive and the life-span is short.For overcoming
All deficiencies of tritiated titanium target, a kind of novel tritium target urgently design and development.And SOFC (SOFC) is new
The design of type tritium target provides thinking.
SOFC is a kind of all solid state system, mainly includes the solid electrolyte of densification, the moon of porous
Pole and the critical material such as anode and fine and close connecting material.The difference of the carrier according to electrolyte conducts, soild oxide fires
Material battery can be divided into oxonium ion (SOFC-O2 -) and proton conduction (SOFC-H+) type fuel cell.For proton conduction type fuel
Battery, its operation principle is:
At anode H2+2O0 ×=2OH+2e-
Gone out electronics by the proton release of Lattice Oxygen ion capture, and by anode-electrolyte interface, pass in electrolyte
Defeated, and arrive negative electrode and oxygen and react generation water.
4OH˙+O2+4e-=2H2O+4O0 ×
After SOFC (SOFC) concept in 1899 is suggested first, solid electrolyte film is many
Individual field obtains considerable application.Ge Ciman (Gottzmann) et al. submits to and general transfers the possession of, and entitled " utilizes solid electrolyte
Film produces the method for hydrogen " United States Patent (USP) (application number 08/848,200) in, disclose ion-conductive membranes and the other equipment of utilizing
Or the combination of process, to improve yield or efficiency.Derna is tieed up strange (Drnevich) et al. and is submitted to and general transfer, entitled
United States Patent (USP) (the application number 08/ " utilizing the solid electrolyte film with combustion gas turbine combination to produce oxidation product and electricity-generating method "
848,258), in, the combination utilizing combustion gas turbine with ion-conductive membranes is disclosed.Between nearest twenty or thirty year, conduct based on proton
The research of material also begins to gradually heat up.Shanghai Communications University is at patent " preparation method of proton-conducting material " (application number
CN200910308552) propose in proton conduction technique is applied to field of inorganic nonmetallic material.The present invention is in above investigation
On the basis of, a set of self-circulation system has been invented in design, proton conductor ceramic membrane can be applied to tritium target, substantially increase tritium target
Use temperature and the utilization rate of tritium.
Summary of the invention
It is an object of the invention to provide a kind of self-loopa tritium containment system based on proton conductor ceramic membrane, be mainly used in deuterium
Tritium fusion neutron generator target system, to put forward operation at high temperature and tritium utilization rate.
The technical solution adopted in the present invention is: a kind of self-loopa tritium containment system based on proton conductor ceramic membrane, including:
The ionization of HTO feed system, HTO and tritium ion conducting system, external power supply, tritium recovering and purifying system；Described HTO ionization
And tritium ion conducting system is in vacuum chamber；The positive pole of external power supply and negative pole ionize and tritium ion conduction system with HTO respectively
The anode of system and negative electrode connect；The ionization of HTO feed system, tritium recovering and purifying system, HTO and tritium ion conducting system seal even
Connect one self circular loop of formation.
Further, HTO ionization and tritium ion conducting system use but are not limited to zinc doping zirconates system as proton
The electrolyte of conductive ceramic film, metal-ceramic is as anode material, and cathode material made by perovskite, and special stainless steel is made to connect material
Material.
Further, by building self-circulation system, it is tritium gas by having neither part nor lot in the tritium ion of fusion reaction in cathodic reduction,
Being drawn into tritium cleaning system by vacuum equipment and be oxidized to HTO once again, recovery Posterior circle returns HTO feed system to be continued to make
With；The tritium amount that participation deuterium tritium fusion reaction is consumed is few, and the HTO in HTO feed system can supplement without the external world for a long time.
The principle of the present invention is:
Self-loopa tritium containment system is built, using proton conductor ceramic membrane as the core of tritium target by rustless steel and quartz glass
Parts.Its self-loopa process is as follows: HTO is fed HTO with certain speed and ionizes and tritium ion conduction by HTO feed system
The tritium ion that the anode HTO ionization of system produces, under extra electric field drives, is migrated by proton conductor ceramic membrane dielectric substrate
After negative electrode, it is reduced to tritium atom and diffuses to electrode surface, by the bombardment generation deuterium tritium fusion of deuterium line.And negative electrode is not joined
Continuing reaction with the tritium atom of fusion reaction and generate tritium gas, the high-temperature oxydation copper through tritium recovering and purifying system is oxidized to tritium once again
Water, collects Posterior circle recuperating depleted YANG pole and is continuing with.Wherein, proton conductor ceramic membrane is sandwich structure, is by fine and close oxide
Ceramiic solid electrolyte and two porous electrodes are constituted.The tritium amount consumed due to participation deuterium tritium fusion reaction is few, and HTO supplies
Can supplement without the external world for a long time to the HTO in system.By regulation applied voltage, it is possible to make tritium ion migration rate and deuterium tritium
Reaction rate matches, and makes tritium utilization rate maximize.
The part such as proton conductor ceramic membrane solid electrolyte, negative electrode, anode and connecting material in self-loopa tritium containment system
It it is all the key factor affecting tritium target performance and life-span.For steady in carbon dioxide and water of equilibrium proton transfer rate and material
Qualitative, can use but be not limited to the zinc doping zirconates system electrolyte as proton conductor ceramic membrane, metal-ceramic conduct
Anode material, perovskite is made cathode material, special stainless steel and quartz glass tube and is made connecting material.
Present invention advantage compared with prior art is:
(1) the tritium target operating temperature of this system of the present invention can improve to 800-1000 DEG C.
(2) present invention, avoiding temperature overheating and cause tritium-thermal desorption, be simultaneously achieved the recycling of tritium, significantly carry
The high utilization rate of tritium.
(3) negative electrode of the present invention put tritium speed can by change applied voltage be adjusted, be allowed to and deuterium tritium fusion reaction speed
Rate matches.
Accompanying drawing explanation
Fig. 1 is the agent structure schematic diagram of the present invention；
Fig. 2 is HTO ionization and the tritium ion conducting system schematic diagram of the present invention.
Wherein: 1. HTO feed system, 2. tritium recovering and purifying system, 3. additional power source, 4. HTO ionization and tritium ion pass
Guiding systems, 5. oxygen outlet, 6. negative electrode, 7. proton conductor electrolyte, 8. anode.
Detailed description of the invention
Below in conjunction with the accompanying drawings, the present invention will be further described.
As shown in Fig. 1 and Fig. 2, a kind of self-loopa tritium containment system based on proton conductor ceramic membrane of the present invention, including HTO
The ionization of feed system 1, tritium recovering and purifying system 2, additional power source 3, HTO and tritium ion conducting system 4；Wherein, HTO ionization and
Tritium ion conducting system 4 is in vacuum chamber, and HTO ionization and tritium ion conducting system 4 include negative electrode 6, proton conductor electrolyte
7 and anode 8, proton conductor electrolyte 7 is between negative electrode 6 and anode 8；The positive pole of external power supply 3 and negative pole are electric with HTO respectively
From and the anode 8 of tritium ion conducting system 4 and negative electrode 6 connect；HTO feed system 1, tritium recovering and purifying system 2 respectively with HTO
Ionization and tritium ion conducting system 4 are tightly connected, and tritium recovering and purifying system 2 is tightly connected with HTO feed system 1, forms one
Closed circuit.
It is embodied as example: open external power supply 3, start self-loopa tritium containment system simultaneously.HTO is by HTO feed system 1
Enter HTO ionization and tritium ion conducting system 4 with certain flow velocity and infiltrate into anode 8, under the effect of extra electric field, HTO
The tritium ion that ionization produces is migrated by proton conductor electrolyte 7, and wherein, proton conductor electrolyte 7 is fine and close oxidation
Thing ceramiic solid electrolyte, anode 8 and negative electrode 6 are porous electrode, and the oxygen that anode electrolysis produces passes through oxygen permeation membrane from oxygen
Gas outlet 5 discharges and collects；Under the effect of electric field, tritium ion passes through proton conductor electrolyte 7, migrates to proton conductor electrolysis
Matter 7 and negative electrode 6 interface.Tritium ion obtains electronics in negative electrode 6 side and is reduced to tritium atom, diffuses to negative electrode 6 by loose structure
Surface also meets with the bombardment generation deuterium tritium fusion of deuterium line.And the tritium atom that negative electrode 6 surface has neither part nor lot in fusion reaction is combined into hydrogen
Gas, departs from electrode and is drawn into tritium recovering and purifying system 2 by vacuum equipment, and being reduced to once again through high-temperature oxydation copper herein
HTO, HTO collection loops back HTO feed system 1 and is continuing with.
What the present invention did not elaborated partly belongs to techniques well known.
Although detailed description of the invention illustrative to the present invention is described above, in order to the technology people of this technology neck
Member understands the present invention, it should be apparent that the invention is not restricted to the scope of detailed description of the invention, and the ordinary skill to the art
From the point of view of personnel, as long as various change limits and in the spirit and scope of the present invention that determine, these become in appended claim
Change is apparent from, and all utilize the innovation and creation of present inventive concept all at the row of protection.
Claims (3)
1. a self-loopa tritium containment system based on proton conductor ceramic membrane, including: HTO feed system (1), HTO ionization and
Tritium ion conducting system (4), external power supply (3), tritium recovering and purifying system (2)；It is characterized in that: described HTO ionization and tritium
Ionic conduction system (4) is in vacuum chamber；The positive pole of external power supply (3) and negative pole conduct with HTO ionization and tritium ion respectively
The anode (8) of system (4) and negative electrode (6) connect；The ionization of HTO feed system (1), tritium recovering and purifying system (2), HTO and tritium
Ionic conduction system (4) is tightly connected one self circular loop of formation.
2. self-loopa tritium containment system based on proton conductor ceramic membrane as claimed in claim 1, it is characterised in that: HTO ionizes
And tritium ion conducting system (4) use but be not limited to the zinc doping zirconates system electrolyte as proton conductor ceramic membrane, gold
Belong to-ceramic as anode material, cathode material made by perovskite, and special stainless steel makees connecting material.
3. self-loopa tritium containment system based on proton conductor ceramic membrane as claimed in claim 1, it is characterised in that: by building
Self-circulation system, is tritium gas by having neither part nor lot in the tritium ion of fusion reaction in cathodic reduction, is drawn into tritium cleaning by vacuum equipment
System is also oxidized to HTO once again, and recovery Posterior circle returns HTO feed system (1) and is continuing with；Participate in deuterium tritium fusion reaction to be disappeared
The tritium amount of consumption is few, and the HTO in HTO feed system (1) can supplement without the external world for a long time.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610671119.0A CN106251912B (en) | 2016-08-15 | 2016-08-15 | Proton conductor ceramic membrane-based self-loop tritium target system |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201610671119.0A CN106251912B (en) | 2016-08-15 | 2016-08-15 | Proton conductor ceramic membrane-based self-loop tritium target system |
Publications (2)
| Publication Number | Publication Date |
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| CN106251912A true CN106251912A (en) | 2016-12-21 |
| CN106251912B CN106251912B (en) | 2017-05-24 |
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| CN201610671119.0A Expired - Fee Related CN106251912B (en) | 2016-08-15 | 2016-08-15 | Proton conductor ceramic membrane-based self-loop tritium target system |
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Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4637866A (en) * | 1983-03-18 | 1987-01-20 | Japan Atomic Energy Research Institute | Recovery method of tritium from tritiated water |
| JPS62210039A (en) * | 1986-03-07 | 1987-09-16 | Japan Atom Energy Res Inst | Method for extracting and transferring tritium |
| CN202989295U (en) * | 2012-08-29 | 2013-06-12 | 中国原子能科学研究院 | Electrolysis concentration apparatus for tritium in environmental water |
| CN104602438A (en) * | 2014-12-29 | 2015-05-06 | 中国原子能科学研究院 | Preparation method of tritium impregnated target slice |
| CN104602439A (en) * | 2015-02-05 | 2015-05-06 | 中国科学院合肥物质科学研究院 | Rotation tritium target device cooled by gallium-indium liquid metal |
| CN104918403A (en) * | 2015-06-26 | 2015-09-16 | 中国工程物理研究院核物理与化学研究所 | Pulsed neutron generator |
| CN204898092U (en) * | 2015-08-20 | 2015-12-23 | 环境保护部核与辐射安全中心 | HTO electrolysis equipment of concentrating |
-
2016
- 2016-08-15 CN CN201610671119.0A patent/CN106251912B/en not_active Expired - Fee Related
Patent Citations (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US4637866A (en) * | 1983-03-18 | 1987-01-20 | Japan Atomic Energy Research Institute | Recovery method of tritium from tritiated water |
| JPS62210039A (en) * | 1986-03-07 | 1987-09-16 | Japan Atom Energy Res Inst | Method for extracting and transferring tritium |
| CN202989295U (en) * | 2012-08-29 | 2013-06-12 | 中国原子能科学研究院 | Electrolysis concentration apparatus for tritium in environmental water |
| CN104602438A (en) * | 2014-12-29 | 2015-05-06 | 中国原子能科学研究院 | Preparation method of tritium impregnated target slice |
| CN104602439A (en) * | 2015-02-05 | 2015-05-06 | 中国科学院合肥物质科学研究院 | Rotation tritium target device cooled by gallium-indium liquid metal |
| CN104918403A (en) * | 2015-06-26 | 2015-09-16 | 中国工程物理研究院核物理与化学研究所 | Pulsed neutron generator |
| CN204898092U (en) * | 2015-08-20 | 2015-12-23 | 环境保护部核与辐射安全中心 | HTO electrolysis equipment of concentrating |
Non-Patent Citations (2)
| Title |
|---|
| G.M.CHENEVERT ET AL: "a tritium gas target as an intense source of 14MeV neutrons", 《NULCEAR INSTRUMENTS AND METHODS》 * |
| 宋健: "质子导体陶瓷膜的制备及其透氢性能", 《中国优秀硕士学位论文全文数据库 工程科技Ⅰ辑》 * |
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Inventor after: Wu Yican Inventor after: Ji Xiang Inventor after: Jiang Jieqiong Inventor after: Wang Chao Inventor after: Wang Shufen Inventor before: Ji Xiang Inventor before: Wu Yican Inventor before: Jiang Jieqiong Inventor before: Wang Chao Inventor before: Wang Shufen |
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Granted publication date: 20170524 Termination date: 20210815 |