CN101630931A - Combined power-generation device of nuclear power and alkali metal thermoelectricity conversion device - Google Patents
Combined power-generation device of nuclear power and alkali metal thermoelectricity conversion device Download PDFInfo
- Publication number
- CN101630931A CN101630931A CN200910072671A CN200910072671A CN101630931A CN 101630931 A CN101630931 A CN 101630931A CN 200910072671 A CN200910072671 A CN 200910072671A CN 200910072671 A CN200910072671 A CN 200910072671A CN 101630931 A CN101630931 A CN 101630931A
- Authority
- CN
- China
- Prior art keywords
- heat
- alkali metal
- steam
- reactor
- nuclear
- 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.)
- Granted
Links
Images
Classifications
-
- 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
- Y02E60/00—Enabling technologies; Technologies with a potential or indirect contribution to GHG emissions mitigation
- Y02E60/14—Thermal energy storage
-
- 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
- Y02E70/00—Other energy conversion or management systems reducing GHG emissions
- Y02E70/30—Systems combining energy storage with energy generation of non-fossil origin
Landscapes
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The invention provides a combined power-generation device of a nuclear power and alkali metal thermoelectricity conversion device. The invention is characterized in that water supply from a secondary circuit side of a steam generator of a nuclear reactor absorbs heat brought out from the reactor by a first circuit alkali metal working medium; the heat is changed into steam in a steam generator; the steam outflows a containment of the nuclear reactor by a main steam pipe from an outlet of the top of the generator, and then enters into a heat exchanger in the interior of a high-temperature phase change heat accumulator; the heat transmission material of the outer wall of the heat exchanger transmits the heat into the heat storage material in the high-temperature phase change heat accumulator; the absorption heat of the heat storage material reaches a heat output interface of the heat accumulator; an alkali metal thermoelectricity direct converter is connected with the heat output interface of the heat accumulator by the heat output interface thereof; the heat enters into the interior of the alkali metal thermoelectricity direct converter to cause the alkali metal thermoelectricity direct converter to work and generate electric energy supplying load. The invention uses the heat emitted by the nuclear reactor as the heat source of the alkali metal thermoelectricity direct converter; the power-generation device is integrated by the nuclear reactor and the alkali metal thermoelectricity direct converter.
Description
(1) technical field
What the present invention relates to is a kind of energy utility system of power energy field, specifically a kind of with the thermal source of nuclear reactor liberated heat as alkali metal thermo-electric direct converter, a kind of Blast Furnace Top Gas Recovery Turbine Unit (TRT) that both are integrated.
(2) background technology
Nuclear reactor is called atomic pile or reactor again, is to have assembled nuclear fuel to realize the device of extensive may command fission chain reaction.The operation principle of nuclear reactor is such: atom is made up of atomic nucleus and electron outside nucleus.Atomic nucleus is made up of proton and neutron.When the atomic nucleus of uranium 235 was subjected to external neutron bombardment, an atomic nucleus can absorb a neutron and split into two atomic nucleus that quality is less, emits 2 to 3 neutrons simultaneously.The neutron that this fission produces goes again to bombard other uranium 235 atomic nucleus, causes new fission.So continuing is exactly the chain reaction of fission.Chain reaction produces a large amount of heat energy.Taking away heat with recirculated water (or other materials) just can avoid reactor to burn because of overheated.The heat of deriving can make water become steam.Hence one can see that, and the most basic composition of nuclear reactor is a fission atom nuclear+heat carrier.But it is inoperable having only these two.Because fast neutron can disperse in a large number, this just need make the chance of neutron degradation increase and nucleus collision; Nuclear reactor will be according to people's wish decision operating state, and this will have control device; Uranium and fission product all have hot, can cause injury to the people, therefore reliable safeguard procedures must be arranged.In sum, the Rational structure of nuclear reactor should be: nuclear fuel+moderator+heat carrier+control device+protector.
According to purposes, nuclear reactor can be divided into the nuclear reaction that 1. following several types is used to neutron beam to test or utilize neutron beam, comprises research reactor, material experiment etc.2. produce radioisotopic nuclear reactor.3. the nuclear reactor of production nuclear fission material is called and produces heap.4. provide the nuclear reactor of the heat of usefulness such as heating, desalinization, chemical industry, such as many purpose heaps.5. the nuclear reaction of heat takes place for generating, is called power generation stack.6. be used to the nuclear reactor that advances boats and ships, aircraft, rocket to wait until, be called propulsion reactor.In addition, nuclear reactor based on fuel type is divided into natural gas uranium reactor, enriched uranium reactor, thorium reactor; Be divided into fast neutron reactor and thermal neutron reactor according to neutron energy; Be divided into water cooled reator, gas-cooled reactor, organic liquor cold dome, liquid metal cold dome according to cooling agent (catalyst carrier) material; Be divided into graphite stack, PHWR, pressure water reactor, boiling-water reactor, stacked organic, MSR, beryllium heap according to moderator (moderator); Be divided into high flux heap and general energetic lump according to neutron flux; Be divided into boiling heap, non-boiling reactor, pressure water reactor according to heat engineering state; Be divided into pulsed reactor and steady-state reactor according to operational mode, or the like.Nuclear reactor is conceptive the design of kind more than 900, but very limited on the reality.
Alkali metal thermo-electric conversion equipment (the Alkali Metal Thermal to Electric converter) is abbreviated as AMTEC, is a kind of novel energy switch technology, and it is a working medium with liquid alkali metal or gaseous bases metal (lithium, potassium, sodium), β " Al
2O
3Solid electrolyte (BASE) is the ion selectivity permeable membrane, and this ceramic material is a good conductor to ion, and almost is insulator to electronics, and this has constituted the basis of alkali metal thermo-electric transducer work.In theory, conversion efficiency of thermoelectric can reach 30%-40%.The thermal power transfer that AMTEC can directly produce solar energy, external firing, radioisotope, reactor thermal source and waste heat becomes electric energy.Alkali metal working medium (liquid state or gaseous state) is moved in closed cycle system, and its transfer process characteristics are isothermal expansion/compression, and therefore isobaric heating can obtain high efficiency.AMTEC has lot of advantages: clean noiseless, compact equipment, little, the suitable dispersed placement of maintenance etc.
Produce huge heat energy during the nuclear reactor nuclear fission, these energy enough guarantee the demand of AMTEC work, therefore can be used as the thermal source of AMTEC.
(3) summary of the invention
The object of the present invention is to provide a kind of huge energy of utilizing the nuclear reactor nuclear fission to emit to make its work produce a kind of nuclear energy and the alkali metal thermo-electric conversion equipment combined power generation device of electric energy for the direct transducer of alkali metal focus provides heat.
The object of the present invention is achieved like this:
Feedwater from the steam generator secondary circuit side of nuclear reactor, a large amount of U type tube walls by steam generator, absorbed the heat that a loop alkali metal working medium brings out from reactor, in steam generator, become steam, steam enters the heat exchanger that is in high-temperature phase change heat accumulation device inside from the additional steam pipe of flowing through the nuclear reactor safety shell is flowed out in the outlet at generator top by main steam pipe after, the outer wall heat-transfer matcrial of heat exchanger is with the heat-storing material in the heat transferred high-temperature phase change heat accumulation device, the absorption heat of heat-storing material arrives the thermal output interface of storage heater, alkali metal thermo-electric direct converter is connected by the thermal output interface of its hot input interface and storage heater, heat enters alkali metal thermo-electric direct converter inside makes its work produce the electric energy supply load, the steam that flows through heat exchanger flows out storage heater and enters condenser condenses after heat is absorbed by the heat-storing material in the storage heater, under the effect of condensate pump, enter the deaerator deoxygenation, under the effect of water supply pump, enter high-pressure heater then and heat at last steam generator admission port by nuclear reactor one loop side and reenter steam generator and absorb heat and circulate.
Between described heat exchanger and the high-temperature phase change heat accumulation device adiabatic sealing device is arranged.
Adopt connector to connect between main steam pipe and the additional steam pipe, the additional steam pipe has heat-insulation layer outward.
Alkali metal is suitable for the cooling agent as nuclear reactor owing to have bigger specific heat.Do the steam generator feedwater that nuclear reactor coolant arrives the heat transferred of reactor core generation steam generator secondary circuit side with alkali metal, when these feedwater flows are crossed the heat exchanger of the high-temperature phase change heat accumulation device inside that is in the secondary circuit side heat is passed to the heat-storing material in the high-temperature phase change heat accumulation device, the high-temperature phase change heat accumulation device is connected with alkali metal thermo-electric direct converter by special interface and guarantees that its working temperature makes alkali metal thermo-electric direct converter work produce electric energy.
The double working medium of doing reactor moderator and cooling agent in the loop among the present invention, under the driving of reactor coolant pump, the reactor core of flowing through, take the nuclear reactor liberated heat out of reactor and arrive steam generator, in of the steam generator feedwater of steam generator one loop side with heat transferred steam generator secondary circuit side, flow through behind the secondary circuit side feedwater outflow containment vessel and be in the heat exchanger of high-temperature phase change heat accumulation device inside, by the heat exchanger outer wall be heat-transfer matcrial with heat transferred high-temperature phase change heat accumulation device, alkali metal thermo-electric direct converter is connected with the high-temperature phase change heat accumulation device by special interface can guarantee that its working temperature makes its work produce electric energy and uses for load.
(4) description of drawings
Fig. 1 is a workflow schematic diagram of the present invention;
Fig. 2 is the connected mode schematic diagram that steam generator exports to heat exchanger;
Fig. 3 is high-temperature phase change heat accumulation device and heat exchanger connected mode schematic diagram;
Fig. 4 is high-temperature phase change heat accumulation device and alkali metal thermo-electric direct converter connected mode schematic diagram.
(5) embodiment
For example the present invention is done description in more detail below in conjunction with accompanying drawing:
In Fig. 1-Fig. 4: 1 is nuclear reactor; 2 is pressurizer; 3 is steam generator; 4 is a loop main condenser agent pump; 5,6 is by-pass valve control; 7 is the steam generator admission port; 8 is the steam generator sewage draining exit; 9 is the high-temperature phase change heat accumulation device; 10 is heat exchanger; 11 is the heat-storing material in the high-temperature phase change heat accumulation device; 12 is condenser; 13 is condensate pump; 14 deaerators; 15 is water supply pump; 16 is high-pressure heater; 17 is alkali metal thermo-electric direct converter; 18 are load; 19 is the nuclear reactor safety shell; 20 is main steam pipe; 21 is connector; 22 is the heat-insulation layer of additional steam pipe; 23 is the additional steam pipe; 24 is heat exchanger; 25 is the afterheat steam discharge line; 26 is the high-temperature phase change heat accumulation device; 27 is the heat-storing material in the high-temperature phase change heat accumulation device; 28 is adiabatic sealing device in the high-temperature phase change heat accumulation device; 29 for the heat exchanger outer wall be heat-transfer matcrial; 30 is the high-temperature phase change heat accumulation wall; 31 is other structures in the storage heater; A, C are respectively the interior vapor stream of heat exchanger and go into outflow port; B is the thermal output port on the high-temperature phase change heat accumulation device; D is the hot input port of alkali metal thermo-electric direct converter; E, F are respectively the temperature end and the low-temperature end of alkali metal thermo-electric direct converter, and a is a loop steam; B is the steam after utilizing.
In conjunction with Fig. 1-Fig. 4, the double alkali metal working medium of doing reactor moderator and cooling agent in one loop, under the driving of reactor coolant pump 4, flow through valve 6 and enter reactor core 1, take the heat that the reactor core nuclear fission discharges out of reactor through valve 5 arrival steam generators 3, working medium needed the adjusting through pressurizer 2 before having gone out reactor core arrival valve 5, pressurizer 2 is connected in major loop (cold leg, before advancing reactor core) and heat pipe section (after going out reactor core) between, can regulate the pressure of reactor core easily, prevent that the temperature of reactor core or pressure from surpassing design condition and cause the accident.The alkali metal heat-transfer working medium that comes out from reactor core arrives behind the steam generator a large amount of U type heat-transfer pipe walls through steam generator, heat steam generator feedwater of passing to the secondary coolant circuit system in the U type pipe outside as much as possible, flow back to reactor coolant pump then, again be pumped into reactor again, absorb the heat energy of reactor core, go out heap again.The sealing circulation circuit in a Here it is loop.The feedwater of steam generator secondary circuit side, a large amount of U type tube walls by steam generator, absorbed the heat that a loop alkali metal working medium brings out from reactor, in steam generator, become steam, enter the heat exchanger 24 that is in high-temperature phase change heat accumulation device 26 inside from the additional steam pipe 23 of flowing through nuclear reactor safety shells 19 are flowed out in the outlet at steam generator top by main steam pipe 20 after, outer wall heat-transfer matcrial 29 by heat exchanger 24 is with the heat-storing material 27 in the heat transferred high-temperature phase change heat accumulation device, heat-storing material absorbs heat makes heat arrive the thermal output interface B of storage heater through the effect of other structures 31 in the storage heater later on, alkali metal thermo-electric direct converter 17 is connected the thermal output interface of its temperature end E and storage heater by its hot input interface D, and heat enters its inside makes its work produce 18 uses of electric energy supply load.The steam that flows through heat exchanger 24 flows out storage heater and enters condenser 12 condensations after heat is absorbed by the heat-storing material in the storage heater 27, under the effect of condensate pump 13, enter deaerator 14 deoxygenations, under the effect of water supply pump 15, enter high-pressure heater 16 then and heat at last steam generator admission port 7 by nuclear reactor one loop side and reenter steam generator and absorb heat and circulate.The sewage draining exit 8 of steam generator can be used to the sewage exhaust steam generator with wherein.
Need to prove have the heat in the adiabatic sealing device 28 assurance storage heaters not reveal between heat exchanger 24 and the high-temperature phase change heat accumulation device 26, as shown in Figure 3; Adopt connector 21 to connect between main steam pipe 20 and the additional steam pipe 23, the additional steam pipe has heat-insulation layer 22 to guarantee that heat is to the environment leakage, as shown in Figure 2 outward.
Claims (3)
1, a kind of nuclear energy and alkali metal thermo-electric conversion equipment combined power generation device, it is characterized in that: from the feedwater of the steam generator secondary circuit side of nuclear reactor, a large amount of U type tube walls by steam generator, absorbed the heat that a loop alkali metal working medium brings out from reactor, in steam generator, become steam, steam enters the heat exchanger that is in high-temperature phase change heat accumulation device inside from the additional steam pipe of flowing through the nuclear reactor safety shell is flowed out in the outlet at generator top by main steam pipe after, the outer wall heat-transfer matcrial of heat exchanger is with the heat-storing material in the heat transferred high-temperature phase change heat accumulation device, the absorption heat of heat-storing material arrives the thermal output interface of storage heater, alkali metal thermo-electric direct converter is connected by the thermal output interface of its hot input interface and storage heater, heat enters alkali metal thermo-electric direct converter inside makes its work produce the electric energy supply load, the steam that flows through heat exchanger flows out storage heater and enters condenser condenses after heat is absorbed by the heat-storing material in the storage heater, under the effect of condensate pump, enter the deaerator deoxygenation, under the effect of water supply pump, enter high-pressure heater then and heat at last steam generator admission port by nuclear reactor one loop side and reenter steam generator and absorb heat and circulate.
2, a kind of nuclear energy according to claim 1 and alkali metal thermo-electric conversion equipment combined power generation device is characterized in that: between described heat exchanger and the high-temperature phase change heat accumulation device adiabatic sealing device is arranged.
3, a kind of nuclear energy according to claim 1 and 2 and alkali metal thermo-electric conversion equipment combined power generation device is characterized in that: adopt connector to connect between main steam pipe and the additional steam pipe, the additional steam pipe has heat-insulation layer outward.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2009100726718A CN101630931B (en) | 2009-08-13 | 2009-08-13 | Combined power-generation device of nuclear power and alkali metal thermoelectricity conversion device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN2009100726718A CN101630931B (en) | 2009-08-13 | 2009-08-13 | Combined power-generation device of nuclear power and alkali metal thermoelectricity conversion device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN101630931A true CN101630931A (en) | 2010-01-20 |
| CN101630931B CN101630931B (en) | 2011-04-20 |
Family
ID=41575911
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN2009100726718A Expired - Fee Related CN101630931B (en) | 2009-08-13 | 2009-08-13 | Combined power-generation device of nuclear power and alkali metal thermoelectricity conversion device |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN101630931B (en) |
Cited By (8)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102878547A (en) * | 2012-10-17 | 2013-01-16 | 亿恒节能科技江苏有限公司 | Outer drying steam triple-effect heat exchange system |
| CN102878548A (en) * | 2012-10-17 | 2013-01-16 | 亿恒节能科技江苏有限公司 | Low humidity steam flash double effect heat exchange system |
| CN109139161A (en) * | 2018-08-29 | 2019-01-04 | 山东电力工程咨询院有限公司 | Nuclear energy and thermoelectricity coupled electricity-generation system and method based on accumulation of heat and gas converting heat |
| CN109405612A (en) * | 2018-11-23 | 2019-03-01 | 重庆岩昱节能科技有限公司 | A kind of liquid metal circulatory system |
| CN111156060A (en) * | 2018-11-08 | 2020-05-15 | 瑞莱国际开发股份有限公司 | Combined type environment-friendly thermal power generation and energy storage system |
| CN111540489A (en) * | 2020-05-21 | 2020-08-14 | 哈尔滨工程大学 | Modular supercritical water cooling and heating pipe reactor system |
| CN113035382A (en) * | 2021-03-04 | 2021-06-25 | 哈尔滨工程大学 | Nuclear reactor system for alkali metal thermoelectric conversion of molten alloy electrode |
| CN114060167A (en) * | 2021-11-16 | 2022-02-18 | 西安交通大学 | Dual-mode nuclear power propulsion device and working method |
Families Citing this family (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102568623B (en) * | 2012-02-28 | 2014-12-03 | 华北电力大学 | Fast neutron reactor and alkali metal thermoelectric converter integrated device for exoplanet |
-
2009
- 2009-08-13 CN CN2009100726718A patent/CN101630931B/en not_active Expired - Fee Related
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102878547A (en) * | 2012-10-17 | 2013-01-16 | 亿恒节能科技江苏有限公司 | Outer drying steam triple-effect heat exchange system |
| CN102878548A (en) * | 2012-10-17 | 2013-01-16 | 亿恒节能科技江苏有限公司 | Low humidity steam flash double effect heat exchange system |
| CN109139161A (en) * | 2018-08-29 | 2019-01-04 | 山东电力工程咨询院有限公司 | Nuclear energy and thermoelectricity coupled electricity-generation system and method based on accumulation of heat and gas converting heat |
| CN109139161B (en) * | 2018-08-29 | 2021-01-29 | 山东电力工程咨询院有限公司 | Nuclear energy and thermal power coupling power generation system and method based on heat storage and gas heat exchange |
| CN111156060A (en) * | 2018-11-08 | 2020-05-15 | 瑞莱国际开发股份有限公司 | Combined type environment-friendly thermal power generation and energy storage system |
| CN109405612A (en) * | 2018-11-23 | 2019-03-01 | 重庆岩昱节能科技有限公司 | A kind of liquid metal circulatory system |
| CN111540489A (en) * | 2020-05-21 | 2020-08-14 | 哈尔滨工程大学 | Modular supercritical water cooling and heating pipe reactor system |
| CN113035382A (en) * | 2021-03-04 | 2021-06-25 | 哈尔滨工程大学 | Nuclear reactor system for alkali metal thermoelectric conversion of molten alloy electrode |
| CN113035382B (en) * | 2021-03-04 | 2022-06-17 | 哈尔滨工程大学 | Nuclear reactor system for alkali metal thermoelectric conversion of molten alloy electrode |
| CN114060167A (en) * | 2021-11-16 | 2022-02-18 | 西安交通大学 | Dual-mode nuclear power propulsion device and working method |
Also Published As
| Publication number | Publication date |
|---|---|
| CN101630931B (en) | 2011-04-20 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN101630931B (en) | Combined power-generation device of nuclear power and alkali metal thermoelectricity conversion device | |
| Şahin et al. | Generation-IV reactors and nuclear hydrogen production | |
| US9111652B2 (en) | High-temperature gas-cooled reactor steam generating system and method | |
| CN103928064B (en) | Thermally-operated conversion system | |
| CN111105883B (en) | Heat pipe reactor system with supercritical carbon dioxide as thermoelectric conversion working medium | |
| CN109147966A (en) | A kind of heat-pipe cooling type nuclear reactor power-supply system based on uranium hydrogen yttrium fuel and dynamic heat to electricity conversion | |
| Pioro et al. | Generation IV nuclear reactors as a basis for future electricity production in the world | |
| JP2016515191A5 (en) | ||
| RU2015113440A (en) | MODULAR TRANSPORTED NUCLEAR GENERATOR | |
| CN102606340B (en) | Power generation system for driving Stirling engine by using heat of spent fuel | |
| Forsberg et al. | An advanced molten salt reactor using high-temperature reactor technology | |
| CN203070789U (en) | Thermally-operated conversion system | |
| CA1245718A (en) | System of generating electricity using a swimming pool type nuclear reactor | |
| CN209216594U (en) | Heat-pipe cooling type reactor power supply based on uranium hydrogen yttrium fuel and dynamic heat to electricity conversion | |
| US2796396A (en) | Method of intermittently operating a neutronic reactor | |
| Duffey et al. | Advanced concepts for pressure-channel reactors: modularity, performance and safety | |
| JP2009115571A (en) | Renewed abwr adapted to combined power generation | |
| JP2005133702A (en) | Combined power-generation by waste-heat utilization | |
| Duffey et al. | SCW pressure-channel nuclear reactors: some design features and concepts | |
| Mitenkov et al. | High-temperature gas-cooled reactors—energy source for industrial production of hydrogen | |
| Zhang et al. | Design considerations for economically competitive sodium cooled fast reactors | |
| Duffey et al. | Advanced cycle efficiency: generating 40% more power from the nuclear fuel | |
| Li et al. | Preliminary analysis of maximum hypothetical accident for a solid core space nuclear reactor power system | |
| Forsberg et al. | Maximizing temperatures of delivered heat from the advanced high-temperature reactor | |
| JP3985024B2 (en) | Fusion power generation system |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| C14 | Grant of patent or utility model | ||
| GR01 | Patent grant | ||
| CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20110420 Termination date: 20180813 |
|
| CF01 | Termination of patent right due to non-payment of annual fee |