CN204087814U - For the fusion products integrated protection device of Z constriction Fusion-fission energy mix heap - Google Patents
For the fusion products integrated protection device of Z constriction Fusion-fission energy mix heap Download PDFInfo
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- CN204087814U CN204087814U CN201420468877.9U CN201420468877U CN204087814U CN 204087814 U CN204087814 U CN 204087814U CN 201420468877 U CN201420468877 U CN 201420468877U CN 204087814 U CN204087814 U CN 204087814U
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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
Abstract
The utility model discloses a kind of fusion products integrated protection device for Z constriction Fusion-fission energy mix heap, belong to nuclear reactor plant field, this Z constriction Fusion-fission energy mix heap is provided with flux of plasma first wall of fusion target center and periphery thereof, it is characterized in that: comprise by fusion target center outwards between flux of plasma first wall, the interior atmosphere layer set gradually, protective cover, outer atmosphere layer and the first wall protective layer, described interior atmosphere layer is made up of the internal layer blanket gas be filled between fusion target center and described shelter-clad, described outer atmosphere layer is made up of the outer protective gas be filled between described shelter-clad and the first wall protective layer, described first wall protective layer is located at described flux of plasma first wall inner wall surface.The utility model be a kind of for Z constriction Fusion-fission energy mix heap, can absorb and protect fusion X ray, ion and fragment, do not affect again By Fusion Neutron transmission, be conducive to simultaneously fusion reaction residue deuterium tritium fuel reclaim protective device.
Description
Technical field
The utility model belongs to nuclear reactor plant field, particularly relates to the protective device for Z constriction Fusion-fission energy mix heap.
Background technology
Z constriction drives fusion-fission energy mix heap (Z-Pinch-Driven Fusion-Fission Hybrid Power Reactor; Z-FFR) Z constriction is utilized to drive inertial confinement fusion (Inertial Confinement Fusion; ICF) a large amount of neutrons produced drive subcritical fission-type reactor and release energy, and are a kind of new forms of energy that can successfully manage future source of energy crisis and amblent air temperature problem.Z-FFR needs the generation that fusion target chamber (Fusion Chamber) is fusion to provide necessary environment, contains fusion products simultaneously and provides fusion function of safety protection.The Z constriction fusion exoergic of energy source use yardstick is about every pulse 1 ~ 3GJ (1GJ=10
9j), wherein the energy of 80% is carried by fusion high-energy neutron, for driving subcritical fission-type reactor exoergic.All the other energy of 20% are carried by X ray, ion (Ions) and fragment (Debris), fusion target chamber flux of plasma first wall (First Wall will be impacted in microsecond time scale, FW), cause the first wall surface ablation and structural failure, affect target chamber safety and operation life.Therefore need one to absorb and protect fusion X ray, ion and fragment, not affecting again the protectiving scheme of By Fusion Neutron transmission.
The sub-National Laboratory (Sandia National Laboratory, SNL) in the U.S. Holy Land proposes Z constriction inertial confinement fusion heap concept " Z-IFE ".The design of its fusion target chamber is for the fusion exoergic of every pulse 3GJ, 0.1Hz running frequency (10 seconds once), thick liquid is adopted to cover (Thick Liquid Curtain) means of defence, namely high-pressure injection fluorine lithium beryllium (Flibe) or lithium lead (LiPb) liquid fused salt (equivalent thickness is about 1m) are as preventive means, fused salt can absorb all fusion products and energy of carrying thereof such as neutron, X ray, is cooling medium, is also the multiplication agent of tritium fuel simultaneously.
Z-IFE concept is pure fusion reactor, utilize thick liquid to cover (Thick Liquid Curtain) method and not only absorb X ray, ion and fragment, also absorb almost whole fusion high-energy neutron, therefore the design of this fusion target chamber is not suitable for Z-FFR (Z-FFR needs strong fusion high-energy neutron to drive subcritical fission-type reactor exoergic, instead of cooled agent absorbs).
Although also can by thinning for thick liquid, to reduce the impact on neutron, but the circulation system of molten salt coolant is inherently very very complicated, and the fused salt injection equipment be arranged in target chamber can increase a large amount of cum rights in target chamber, the reliability of these mechanisms in the extreme harsh environment of target chamber and long-time running life-span are difficult to ensure.
The sub-National Laboratory in the U.S. Holy Land it is also proposed Z constriction and drives transmuting heap concept " In-Zinerator ", for the spentnuclear fuel that the existing fissioning nucleus power station of transmuting produces.The design of its fusion target chamber is for the fusion exoergic of every pulse 0.2GJ, 0.1Hz running frequency (10 seconds once), and energy Ratios Z-IFE and Z-FFR that fusion X ray, ion and fragment carry is much smaller.In-Zinerator adopts the Ar gas/gasoloid filling 1000 ~ 2000Pa in target chamber to absorb the preventive means of fusion X ray.
In-Zinerator each fusion exoergic 0.2GJ, the energy that fusion X ray carries is about 50MJ (1MJ=10
6j), relatively Z-IFE and Z-FFR is much smaller, therefore adopt simply fill Ar gas/aerosol method can absorption of x-rays.
And Z-FFR fusion X-ray energy is about 200MJ ~ 600MJ, 1000 ~ 2000Pa gasoloid can not absorb completely.Although raising inflation pressure and aerosol concentration can absorb whole X-ray energy, also can produce extremely strong shock wave in target chamber simultaneously, safely serious threat is caused to the first wall.
In addition, the gasoloid protectiving scheme of In-Zinerator well can not protect fusion fragment (Debris).
Utility model content
The purpose of this utility model is: a kind of for Z constriction Fusion-fission energy mix heap, can absorb and protect fusion X ray, ion and fragment, do not affect again By Fusion Neutron transmission, be conducive to simultaneously fusion reaction residue deuterium tritium fuel reclaim protective device.
The utility model object is realized by following technical proposals:
A kind of fusion products integrated protection device for Z constriction Fusion-fission energy mix heap, this Z constriction Fusion-fission energy mix heap is provided with flux of plasma first wall of fusion target center and periphery thereof, it is characterized in that: comprise by fusion target center outwards between flux of plasma first wall, the interior atmosphere layer set gradually, protective cover, outer atmosphere layer and the first wall protective layer, described interior atmosphere layer is made up of the internal layer blanket gas be filled between fusion target center and described shelter-clad, described outer atmosphere layer is made up of the outer protective gas be filled between described shelter-clad and the first wall protective layer, described first wall protective layer is located at described flux of plasma first wall inner wall surface.
In such scheme, protective cover mainly bears the protection task of fusion kinetic energy fragment, and also providing unit divides fusion X ray and ion safeguard function simultaneously.Fusion reaction product comprises strong X ray, ion and kinetic energy fragment etc., and single employing atmosphere can protect fusion X ray and ion, but cannot solve the protection question of fusion kinetic energy fragment, therefore proposes protective cover protection Design.Main Function process: a large amount of fusion ions that fusion reaction produces and fragment are stoped by protective cover; gasified together with protective cover by the strong X ray that fusion reaction produces and move to flux of plasma first wall subsequently; in motion process, gasification product lower the temperature by outer atmosphere layer buffering and slows down, final formation metal particle set out by outer atmosphere layer and in subsequent process separating treatment.Protective cover design solves a protection difficult problem for fusion kinetic energy fragment; by the parameter such as material, radius, thickness of computational analysis means reasonable adjusting protective cover; can realize both having stoped fusion kinetic energy fragment, can be gasified totally by strong X ray again, avoid the formation of new fragment and clash into the first wall.
Atmosphere in target chamber is divided into two parts by protective cover: interior atmosphere layer provides environment needed for the fusion load of Z constriction and fusion target, and slightly regulates protective cover vaporization time; Outer atmosphere layer provides safeguard function, absorbs main fusion X ray and ion energy, simultaneously as the buffering of kinetic energy impact.Mechanism: continued to be absorbed by outer atmosphere layer by the residue X ray after protective cover absorbs a part, its ectonexine blanket gas heats up to expand and form shock wave and moves to flux of plasma first wall.Meanwhile, vaporized fusion ions, fragment and protective cover slow down in atmosphere layer outside and cool gradually, impact flux of plasma first wall together with outer protective gas.In the process; protective cover and outer atmosphere layer absorb fusion X ray, ion and the fragment energy of more than 99%; and these harmful energy opposites are expanded to several ms to the attack time yardstick of plasma first wall by microsecond; significantly reduce the ablation to flux of plasma first wall and impact strength, improve the security of Z-FFR.
In the end the first wall protective layer of link adopts high temperature resistant tungsten or molybdenum alloy coating, improves resistance to thermal ablation and the impact property of flux of plasma first wall, guarantees the safe and reliable of flux of plasma first wall further.
As selection, described interior atmosphere layer and/or outer atmosphere layer are filled by the inert gas of atomic number >=18.
In such scheme, internal layer blanket gas and the gaseous medium of filling in outer protective gas can identical also can be different.
As selection, described interior atmosphere layer and/or outer atmosphere layer are by Ar, Xe, N
2or air is filled.The mixed gas that can also be made up of the multiple gases in These gases, or pure gas or mixed gas and water drop, the gasoloid that Al or Fe metal particle is formed is filled.
Described gasoloid (aerosol) is disperseed by solid or liquid fine particle and is suspended in the colloidal dispersion system formed in gas medium, also known as gas dispersion system.Its disperse phase is solid or liquid fine particle, and its size is 0.001 ~ 100 micron, and dispersion medium is gas.
As further selecting, described interior atmosphere layer is the Ar gas of pressure 10 ~ 1000Pa, outer atmosphere layer be pressure 500Pa ~ 2000Pa Ar gas.
In such scheme, adopt argon gas, and particular pressure, be enough to the fusion X-ray energy of absorption more than 99.9%, stronger shock impingement flux of plasma first wall can not be produced again, taken into account X-ray energy simultaneously and to have absorbed and impact strength controls the rigors of two aspects.As adopted the Xe gas higher than argon gas atmo ordinal number, its pressure can reduce slightly.As adopted N
2or air, its initial pressure needs to improve further.
As selection, described protective cover is Metal Ball shell structure, is greater than 200MPa by atomic number 12 ~ 26, structural strength, and the metal of the fusion X ray that can be produced by fusion target center gasification or its alloy are made.
Described alloy is the material with metallic character synthesized by two or more metal and the certain method of nonmetal warp.The metal of component alloy all or part ofly can be greater than 200MPa by aforementioned atomic number 12 ~ 26, structural strength, and the metal of the fusion X ray that can be produced by fusion target center gasification or its alloy are made.
As further selection, described protective cover is made up of carbon steel, Al, Al base alloy or Ti base alloy.
Described carbon steel mainly refers to the iron-carbon alloy that the massfraction of carbon is less than 2.11%.Sometimes also referred to as straight carbon steel or carbon steel.
The optional Al75/Si25 alloy of described Al base alloy, Al95/Mg5 alloy.
Described Ti base alloy (Titanium base alloys (Ti-based)) optional TiAl alloy, Ti
3al alloy.
As further selecting, described protective cover is made up of Al or carbon steel, radius 25 ~ 100cm, wall thickness 0.2 ~ 1.0mm.
In such scheme, adopt carbon steel, and specific restriction size, both can stop fusion kinetic energy fragment, can be gasified totally by fusion X ray again, finally realize fusion fragment protective object.
As selection, described first wall protective layer is made up of the material more than resistance to 1300 DEG C of temperature, more than resistance to 1MPa impact strength.
As further selection, described first wall protective layer is made up of tungsten, molybdenum alloy, tungalloy or SiC ceramic.
The optional W-1%La of described tungalloy
2o
3alloy, W-TiC alloy, W-5 ~ 25%Re alloy, W-Cu Functionally Graded Materials etc. have the tungsten alloy material of higher force intensity.
The optional Mo-Ti-Zr alloy of described molybdenum alloy and Mo-W alloy etc. have the molybdenum alloy material of higher force intensity and recrystallization temperature.
As further selecting, described first wall protective layer is the tungsten coating of flux of plasma first wall inner wall surface, thick coating 0.1mm ~ 1.0mm.
In such scheme, adopt tungsten, and specific thicknesses, both can stop X ray completely, and there is again necessary structural strength, improve the safety and reliability of flux of plasma first wall.
In aforementioned approaches case of the present invention, involved various material all can commercially availablely be buied, and can select combination during enforcement as required.
The main scheme of aforementioned the utility model and each further selection scheme thereof can independent assortment to form multiple scheme; be the utility model can adopt and claimed scheme: as the utility model; each selection can select combination in any with other; those skilled in the art can understand there is multiple combination according to prior art and common practise after understanding the utility model scheme; be the claimed technical scheme of the utility model, do not do exhaustive at this.
The utility model relates to abbreviation and Key Term definition:
Z constriction---the superpower electromagnetic force utilizing large-drive-current to produce drives load plasma implosion thus realizes a kind of technological approaches of fusion;
Z-FFR---Z constriction drives fusion-fission energy mix heap (Z-Pinch-Driven Fusion-Fission Hybrid Power Reactor), and what Peng person with foresight academician and China Engineering Physics Research Institute proposed utilizes Z constriction By Fusion Neutron to drive subcritical fission-type reactor thus energy-producing energy pile concept;
ICF---inertial confinement fusion (Inertial Confinement Fusion);
FW---flux of plasma first wall (First Wall);
Z-IFE---the Z constriction inertial confinement fusion energy concept that the sub-National Laboratory in the U.S. Holy Land proposes is pure fusion power energy pile;
In-Zinerator---the Z constriction that the sub-National Laboratory in the U.S. Holy Land proposes drives transmuting heap concept, for the spentnuclear fuel that the existing fissioning nucleus power station of transmuting produces.
The beneficial effects of the utility model: the integrated protection device of the fusion X ray for Z constriction Fusion-fission energy mix heap of the present utility model, ion and fragment; by protective cover, atmosphere and the first wall protective layer composite design; simply, effectively can realize fusion function of safety protection, be applicable to Z-FFR application, the 0.1Hz running frequency of Z-FFR can be solved, strong fusion X ray that 1 ~ 3GJ fusion exoergic state produces, ion and the concrete effect of fragment integrated protection problem comprise:
1. 200MJ ~ 600MJ level fusion X ray, high energy charged ion and kinetic energy fragment that Z-FFR fusion process produces can effectively be protected;
2. safeguard procedures are simple, only in target chamber, introduce a small amount of structure and material, can ignore the impact of fusion high-energy neutron;
3. the shock strength produced in target chamber is only several atmospheric pressure, very little on the impact of the first wall construction;
4. these safeguard procedures use inert gas and metal material, are gas and metal particle after fusion, are easily separated and realize the recycling that fusion reaction remains deuterium tritium fuel.
Accompanying drawing explanation
Fig. 1 is the structural representation of the utility model embodiment 1;
1 be wherein MITL (magnetic insulation transmission line), 2 be RTL (replaceable transmission line), 3 be fusion target center, 4 be interior atmosphere layer, 5 be protective cover, 6 for outer atmosphere layer, 7 be that the first wall protective layer, 8 is for flux of plasma first wall.
Embodiment
Following non-limiting examples is for illustration of the utility model.
Embodiment 1:
Shown in figure 1, a kind of integrated protection device for Z constriction Fusion-fission energy mix heap, this Z constriction Fusion-fission energy mix heap is provided with flux of plasma first wall 8 of fusion target center 3 and periphery thereof, comprise by fusion target center 3 outwards between flux of plasma first wall 8, the interior atmosphere layer 4 set gradually, protective cover 5, outer atmosphere layer 6 and the first wall protective layer 7, interior atmosphere layer 4 is made up of the internal layer blanket gas be filled between fusion target center 3 and shelter-clad 5, outer atmosphere layer 6 is made up of the outer protective gas be filled between shelter-clad 5 and the first wall protective layer 7, first wall protective layer 7 is located at flux of plasma first wall 8 inner wall surface.Internal layer blanket gas is the Ar gas of pressure 1000Pa, outer protective gas be pressure 1000Pa Ar gas.Protective cover 5 is made up of Al, radius 40cm, wall thickness 0.3mm.First wall protective layer 7 is the tungsten coating of flux of plasma first wall 8 inner wall surface, thick coating 0.15mm.Utilize Fluid Dynamic Equations With Radiation model calculation program to calculate under 1.5GJ fusion exoergic condition, final Protection Results is: the first wall inside surface radiant flux density is by about 50J/cm when not adding protection
2be down to 0.006J/cm
2, peak of radiation stream power density 2.1W/cm
2, the impact strength that the first wall is subject to simultaneously is 0.25MPa, and the two is much smaller than the first wall safety limit; Be fully vaporized prior in 3 μ s after fusion kinetic energy fragment covers on fusion together with metal coating, transient temperature about 16000 DEG C, be cooled to less than 700 DEG C gradually in atmosphere outside subsequently; System leading indicator meets security protection requirement.
Embodiment 2:
The present embodiment is substantially the same manner as Example 1, and its difference is that internal layer blanket gas is the Ar gas of pressure 500Pa, and outer protective gas is the Ar gas of pressure 500Pa.Protective cover is made up of Al, radius 50cm, wall thickness 0.25mm.First wall protective layer is the W-10%Re alloy of flux of plasma first wall inner wall surface, thick coating 0.2mm.Utilize Fluid Dynamic Equations With Radiation model calculation program to calculate under 1.5GJ fusion exoergic condition, final Protection Results is: the first wall inside surface radiant flux density is by about 50J/cm when not adding protection
2be down to 0.015J/cm
2, peak of radiation stream power density 7W/cm
2, the impact strength that the first wall is subject to simultaneously is 0.20MPa, and the two is much smaller than the first wall safety limit; Be fully vaporized prior in 4 μ s after fusion kinetic energy fragment covers on fusion together with metal coating, transient temperature about 12000 DEG C, be cooled to less than 800 DEG C gradually in atmosphere outside subsequently; System leading indicator meets security protection requirement.
Embodiment 3:
The present embodiment is substantially the same manner as Example 2, and its difference is that internal layer blanket gas is the Ar gas/Al gasoloid of pressure 100Pa, and outer protective gas is the Ar gas/Al gasoloid of pressure 250Pa.Protective cover is made up of Al metal, radius 60cm, wall thickness 0.2mm.First wall protective layer is the W-10%Re alloy of flux of plasma first wall inner wall surface, thick coating 0.2mm.Utilize Fluid Dynamic Equations With Radiation model calculation program to calculate under 1.5GJ fusion exoergic condition, final Protection Results is: the first wall inside surface radiant flux density is by about 50J/cm when not adding protection
2be down to 0.06J/cm
2, peak of radiation stream power density 42W/cm
2, the impact strength that the first wall is subject to simultaneously is 0.25MPa, and the two is much smaller than the first wall safety limit; Be fully vaporized prior in 5 μ s after fusion kinetic energy fragment covers on fusion together with metal coating, transient temperature about 10000 DEG C, be cooled to less than 1100 DEG C gradually in atmosphere outside subsequently; System leading indicator meets security protection requirement.
Embodiment 4:
The present embodiment is substantially the same manner as Example 1, and its difference is that internal layer blanket gas is the Ar gas of pressure 100Pa, and outer protective gas is the Ar gas of pressure 500Pa.Protective cover is made up of carbon steel, radius 50cm, wall thickness 0.25mm.First wall protective layer is the W coating of flux of plasma first wall inner wall surface, thick coating 0.15mm.Utilize Fluid Dynamic Equations With Radiation model calculation program to calculate under 1.5GJ fusion exoergic condition, final Protection Results is: the first wall inside surface radiant flux density is by about 50J/cm when not adding protection
2be down to 0.03J/cm
2, peak of radiation stream power density 12W/cm
2, the impact strength that the first wall is subject to simultaneously is 0.28MPa, and the two is much smaller than the first wall safety limit; Be fully vaporized prior in 6 μ s after fusion kinetic energy fragment covers on fusion together with metal coating, transient temperature about 11000 DEG C, be cooled to less than 800 DEG C gradually in atmosphere outside subsequently; System leading indicator meets security protection requirement.
The foregoing is only preferred embodiment of the present utility model; not in order to limit the utility model; all do within spirit of the present utility model and principle any amendment, equivalent to replace and improvement etc., all should be included within protection domain of the present utility model.
Claims (10)
1. the fusion products integrated protection device for Z constriction Fusion-fission energy mix heap, this Z constriction Fusion-fission energy mix heap is provided with flux of plasma first wall of fusion target center and periphery thereof, it is characterized in that: comprise by fusion target center outwards between flux of plasma first wall, the interior atmosphere layer set gradually, protective cover, outer atmosphere layer and the first wall protective layer, described interior atmosphere layer is made up of the internal layer blanket gas be filled between fusion target center and described shelter-clad, described outer atmosphere layer is made up of the outer protective gas be filled between described shelter-clad and the first wall protective layer, described first wall protective layer is located at described flux of plasma first wall inner wall surface.
2., as claimed in claim 1 for the fusion products integrated protection device of Z constriction Fusion-fission energy mix heap, it is characterized in that: described interior atmosphere layer and/or outer atmosphere layer are filled by the inert gas of atomic number >=18.
3., as claimed in claim 1 for the fusion products integrated protection device of Z constriction Fusion-fission energy mix heap, it is characterized in that: described interior atmosphere layer and/or outer atmosphere layer are by Ar, Xe, N
2or air is filled.
4. as claimed in claim 3 for the fusion products integrated protection device of Z constriction Fusion-fission energy mix heap, it is characterized in that: described interior atmosphere layer is the Ar gas of pressure 10 ~ 1000Pa, outer atmosphere layer be pressure 500Pa ~ 2000Pa Ar gas.
5. as claimed in claim 1 for the fusion products integrated protection device of Z constriction Fusion-fission energy mix heap; it is characterized in that: described protective cover is Metal Ball shell structure; by atomic number 12 ~ 26; structural strength is greater than 200MPa, and the metal of the fusion X ray that can be produced by fusion target center gasification or its alloy are made.
6., as claimed in claim 5 for the fusion products integrated protection device of Z constriction Fusion-fission energy mix heap, it is characterized in that: described protective cover is made up of carbon steel, Al, Al base alloy or Ti base alloy.
7., as claimed in claim 6 for the fusion products integrated protection device of Z constriction Fusion-fission energy mix heap, it is characterized in that: described protective cover is made up of Al or carbon steel, radius 25 ~ 100cm, wall thickness 0.2 ~ 1.0mm.
8., as claimed in claim 1 for the fusion products integrated protection device of Z constriction Fusion-fission energy mix heap, it is characterized in that: described first wall protective layer is made up of the material more than resistance to 1300 DEG C of temperature, more than resistance to 1MPa impact strength.
9., as claimed in claim 8 for the fusion products integrated protection device of Z constriction Fusion-fission energy mix heap, it is characterized in that: described first wall protective layer is made up of tungsten, molybdenum alloy, tungalloy or SiC ceramic.
10., as claimed in claim 9 for the fusion products integrated protection device of Z constriction Fusion-fission energy mix heap, it is characterized in that: described first wall protective layer is the tungsten coating of flux of plasma first wall inner wall surface, thick coating 0.1mm ~ 1.0mm.
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| CN201420468877.9U CN204087814U (en) | 2014-08-19 | 2014-08-19 | For the fusion products integrated protection device of Z constriction Fusion-fission energy mix heap |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104134470A (en) * | 2014-08-19 | 2014-11-05 | 中国工程物理研究院核物理与化学研究所 | Fusion product comprehensive protection device for Z-hoop condensation polymerization fission energy pile |
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2014
- 2014-08-19 CN CN201420468877.9U patent/CN204087814U/en not_active Withdrawn - After Issue
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN104134470A (en) * | 2014-08-19 | 2014-11-05 | 中国工程物理研究院核物理与化学研究所 | Fusion product comprehensive protection device for Z-hoop condensation polymerization fission energy pile |
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| GR01 | Patent grant | ||
| AV01 | Patent right actively abandoned |
Granted publication date: 20150107 Effective date of abandoning: 20160629 |
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| C25 | Abandonment of patent right or utility model to avoid double patenting |