CN110232979B - Open grid type gas-cooled space nuclear reactor core - Google Patents
Open grid type gas-cooled space nuclear reactor core Download PDFInfo
- Publication number
- CN110232979B CN110232979B CN201910509025.7A CN201910509025A CN110232979B CN 110232979 B CN110232979 B CN 110232979B CN 201910509025 A CN201910509025 A CN 201910509025A CN 110232979 B CN110232979 B CN 110232979B
- Authority
- CN
- China
- Prior art keywords
- reflecting layer
- reactor core
- fuel
- gas
- fuel rod
- 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.)
- Active
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/10—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from reflector or thermal shield
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
-
- 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
- Y02E30/30—Nuclear fission reactors
Abstract
The invention belongs to the technical field of nuclear reactors and discloses a nuclear reactor core of an open grid type gas-cooled space, which comprises a core active area, a core barrel, a radial reflecting layer and control rods; the reactor core active area is positioned in the reactor core barrel and consists of a plurality of fuel rods; the radial reflecting layer is of a hollow cylindrical structure, is divided into an inner layer and an outer layer, wraps the outer side of the reactor core barrel and is as high as the reactor core barrel; the fuel rods and the control rods are distributed in the core active area; the fuel rods and the control rods are positioned by the upper grid plate and the lower grid plate and the wire winding wound on the cladding of the upper grid plate and the lower grid plate; the fuel rod is internally composed of hollow cylindrical fuel pellets and is filled with helium, and two ends of the interior of the fuel rod are provided with axial reflecting blocks; the reactor core and the reflecting layer are both cooled by helium-xenon mixed gas; the reactor core can provide megawatt high-power electric energy for space tasks and has the advantages of light weight and compactness.
Description
Technical Field
The invention relates to the technical field of nuclear reactors, in particular to a nuclear reactor core of an open grid type gas-cooled space.
Background
The gas-cooled space nuclear reactor is cooled by helium-xenon mixed gas, and high-temperature gas flowing out of the reactor can be directly connected with Brayton cycle components, so that high thermoelectric conversion efficiency can be achieved, and the gas-cooled space nuclear reactor is paid attention to in high-power space application.
The core of the nuclear reactor with the gas-cooled space proposed at present mainly comprises a pebble bed type, a hexagonal prism type and a refractory metal matrix type. The pebble bed type reactor core is characterized in that fuel is made into a spherule shape, and a coolant flows among pebble beds to take away fission heat energy; the hexagonal prism type means that the metal ceramic fuel is made into a hexagonal prism shape, and a plurality of cylindrical pore channels are formed in the middle of the metal ceramic fuel and used for flowing of a coolant; the refractory metal matrix type is that refractory metal is made into a core matrix, a plurality of cylindrical pore channels are arranged in the middle of the core matrix, fuel rods or control rods are inserted into the pore channels, and a coolant flows in an annular channel between the core matrix and the fuel rods (control rods).
The core design of the three gas cooled space nuclear reactors has advantages, but the common disadvantage is that the weight is often too heavy, and high requirements are made on the emission of the space nuclear reactor. The invention aims to disclose a light and compact gas-cooled space nuclear reactor core design, namely an open grid type gas-cooled space nuclear reactor core.
Disclosure of Invention
The invention aims to provide a reactor core of an open grid type gas-cooled space nuclear reactor, which provides a high-power, light and compact reactor core design scheme for the space nuclear reactor.
In order to achieve the purpose, the invention adopts the following technical scheme:
the open grid type gas-cooled space nuclear reactor core comprises a reactor core active area 16, a reactor core cylinder 4 coated on the periphery of the reactor core active area, and two reflecting layers, namely an inner reflecting layer 7 and an outer reflecting layer 5 coated on the outer side of the reactor core cylinder 4; the reactor core active region 16 consists of a plurality of fuel rods 2 and a plurality of control rods 3, and the fuel rods 2 and the control rods 3 are arranged in a triangular or rectangular grid to form an open space for the flow of the coolant;
the fuel rod 2 sequentially comprises fuel pellets 12, a fuel rod gas gap 13-1 and a fuel rod cladding 14-1 from inside to outside; axial reflection blocks 11 are filled in the fuel rod cladding 14-1 and at two ends of the fuel pellet 12, and connecting pieces 10-1 at the end parts of the fuel rods are arranged at two ends of the fuel rods 2; the control rod 3 sequentially comprises a neutron absorber 17, a control rod air gap 13-2 and a control rod cladding 14-2 from inside to outside, and two ends of the control rod 3 are control rod end connecting pieces 10-2; the fuel rod gas gap 13-1 and control rod gas gap 13-2 are used to accommodate thermal expansion of fission gases and materials.
The upper ends and the lower ends of the fuel rods 2 and the control rods 3 are respectively positioned by an upper grid plate 8 and a lower grid plate 9, and a fuel rod wire winding 15-1 wound on a fuel rod cladding 14-1 and a control rod wire winding 15-2 wound on a control rod cladding 14-2;
the main body structures of the inner reflecting layer 7 and the outer reflecting layer 5 are made of beryllium oxide, and a plurality of reflecting layer coolant inlet channels 6 and reflecting layer coolant outlet channels 1 are respectively arranged in the inner reflecting layer 7 and the outer reflecting layer 5; the reflecting layer coolant enters from the lower end of the reflecting layer coolant inlet channel 6 and flows out from the reflecting layer coolant outlet channel 1 in the outer reflecting layer 5 in a baffling mode after reaching the upper portion of the inner reflecting layer 7, and the function of cooling the reflecting layer is achieved.
The coolant in the core active region 16 is a helium-xenon mixed gas, flows from the lower portion of the core to the upper portion of the core, and carries away the energy generated by the fission of the fuel in the fuel rod 2 as a heat carrier.
The material of the fuel pellet 12 in the fuel rod 2 is uranium dioxide, the enrichment degree is not less than 90%, and the fuel pellet is of a hollow cylindrical structure.
The fuel rod winding 15-1 and the control rod winding 15-2 are made of tungsten-rhenium alloy, and the fuel rod cladding 14-1 and the control rod cladding 14-2 are made of tungsten-rhenium alloy.
Helium is filled in the fuel rod gas gap 13-1 and the control rod gas gap 13-2.
The axial reflection blocks 11 at two ends inside the fuel rod 2 are made of tungsten.
The neutron absorber 17 filled in the control rod 2 is made of boron carbide.
The inner reflecting layer 7 and the outer reflecting layer 5 are made of beryllium oxide, and a helium-xenon mixed gas is adopted as a coolant in the inner reflecting layer 7 and the outer reflecting layer 5, wherein the molecular weight of the helium-xenon mixed gas is 38-42 g/mol.
Compared with the prior art, the invention has the following advantages:
1) the invention adopts an open grid type structure, avoids the use of a refractory alloy matrix of the reactor core, and obviously lightens the weight of the reactor core of the nuclear reactor.
2) According to the invention, the reactor core coolant adopts helium-xenon mixed gas with the molecular weight of 38-40 g/mol, and the number of Brayton cycle stages can be reduced under the condition of considering the heat exchange effect, so that the total weight of the nuclear reactor system is reduced.
3) The fuel rods and the control rod cladding are wound with the wire winding, so that the positioning function is realized, the functions of enhancing the mixing of the coolant and enhancing the heat exchange are realized, the heat exchange efficiency is improved, and the weight of the reactor core of the spatial nuclear reactor can be effectively reduced.
4) The axial reflection blocks are arranged in the fuel rods, so that the axial reflection layers are prevented from being arranged on the upper portion and the lower portion of the reactor core cavity respectively, and the total weight of the reactor core can be effectively reduced.
Drawings
FIG. 1 is a schematic cross-sectional view of a nuclear reactor core in an open grid gas cooled space according to the present invention.
FIG. 2 is a schematic longitudinal cross-sectional view of a nuclear reactor core in an open grid gas cooled space according to the present invention.
FIG. 3 is a longitudinal cross-sectional schematic view of a fuel rod.
FIG. 4 is a schematic cross-sectional view of a fuel rod.
FIG. 5 is a longitudinal cross-sectional schematic view of a control rod.
FIG. 6 is a cross-sectional schematic view of a control rod.
Detailed Description
The present invention will be described in further detail with reference to the accompanying drawings.
As shown in fig. 1 and 2, the open grid type gas-cooled space nuclear reactor core of the present invention includes a core active region 16, a core barrel 4 covering the periphery of the core active region, and two reflecting layers (an inner reflecting layer 7 and an outer reflecting layer 5) covering the outer side of the core barrel 4; the core active region 16 is composed of a plurality of fuel rods 2 and a plurality of control rods 3. The fuel rods 2 and the control rods 3 are arranged in a triangular or rectangular lattice to constitute an open space in which a coolant flows.
As shown in fig. 3 and 4, the fuel rod 2 includes fuel pellets 12, a fuel rod gas gap 13-1, and a fuel rod clad 14-1 in this order from the inside to the outside.
As shown in fig. 5 and 6, the control rod 3 comprises a neutron absorber 17, a control rod gas gap 13-2 and a control rod cladding 14-2 in sequence from inside to outside;
as shown in fig. 2 to 6, the upper and lower ends of the fuel rod 2 and the control rod 3 are positioned by the upper and lower grid plates 8 and 9, respectively, and the fuel rod wire 15-1 wound on the fuel rod cladding 14-1 and the control rod wire 15-2 wound on the control rod cladding 14-2. Axial reflection blocks 11 are filled in the fuel rod cladding 14-1 and at two ends of the fuel pellet 12, and connecting pieces 10-1 at the end parts of the fuel rods are arranged at two ends of the fuel rods 2; two ends of the control rod 3 are control rod end connectors 10-2, and the control rod end connectors 10-1 and the control rod end connectors 10-2 are fixed on the upper grid plate 8 and the lower grid plate 9.
The main body structures of the inner reflecting layer 7 and the outer reflecting layer 5 are made of beryllium oxide, and a plurality of reflecting layer coolant inlet channels 6 and reflecting layer coolant outlet channels 1 are respectively arranged in the inner reflecting layer 7 and the outer reflecting layer 5. The reflecting layer coolant enters from the lower end of the reflecting layer coolant inlet channel 6 and flows out from the reflecting layer coolant outlet channel 1 in the outer reflecting layer 5 in a baffling mode after reaching the upper portion of the inner reflecting layer 7, and the function of cooling the reflecting layer is achieved.
The coolant in the core active region 16 is a helium-xenon mixed gas, flows from the lower portion of the core to the upper portion of the core, and carries away the energy generated by the fission of the fuel in the fuel rod 2 as a heat carrier.
The fuel rod gas gap 13-1 and control rod gas gap 13-2 are to contain fission gases.
As a preferred embodiment of the invention, the number of fuel rods 2, control rods 3 and cooling channels of the inner and outer reflective layers 7, 5 is determined according to the reactor power requirements.
In a preferred embodiment of the present invention, the material of the fuel core 12 in the fuel rod 2 is uranium dioxide, and the enrichment degree is not less than 90%, and the fuel core is a hollow cylindrical structure.
As a preferred embodiment of the present invention, the material of the fuel rod winding 15-1 and the control rod winding 15-2 is tungsten-rhenium alloy.
As a preferred embodiment of the invention, the material of the fuel rod cladding 14-1 and the control rod cladding 14-2 is tungsten-rhenium alloy, and the filling gas in the fuel rod gas gap 13-1 and the control rod gas gap 13-2 is helium.
In a preferred embodiment of the present invention, the material of the axial reflector blocks 11 at both ends inside the fuel rod 2 is tungsten.
In a preferred embodiment of the present invention, the neutron absorber 17 filled in the control rod 2 is made of boron carbide.
As a preferred embodiment of the present invention, the material of the inner reflective layer 7 and the outer reflective layer 5 is beryllium oxide.
In a preferred embodiment of the invention, helium-xenon mixed gas is used as the coolant in the inner reflecting layer 7 and the outer reflecting layer 5, and the molecular weight is 38-40 g/mol.
To better illustrate the design, the working principle is now described:
helium-xenon cooling gas flows through the core active area from bottom to top to carry away fission energy generated by fuel; meanwhile, helium xenon cooling gas of the other branch enters the inner reflecting layer 7 from the reflecting layer coolant inlet channel 6 in the inner reflecting layer 7, and flows out from the reflecting layer coolant outlet channel 1 in the outer reflecting layer 5 in a baffling manner after reaching the upper part of the inner reflecting layer 7, so that the effect of cooling the reflecting layer is achieved.
Claims (8)
1. An open grid type gas-cooled space nuclear reactor core, characterized in that: the reactor core comprises a reactor core active region (16), a reactor core cylinder (4) coated on the periphery of the reactor core active region, and two reflecting layers, namely an inner reflecting layer (7) and an outer reflecting layer (5), coated on the outer side of the reactor core cylinder (4); the reactor core active region (16) consists of a plurality of fuel rods (2) and a plurality of control rods (3), and the fuel rods (2) and the control rods (3) are arranged in a triangular or rectangular grid manner to form an open space for the flow of the coolant;
the fuel rod (2) sequentially comprises fuel pellets (12), a fuel rod gas gap (13-1) and a fuel rod cladding (14-1) from inside to outside; axial reflecting blocks (11) are filled in the fuel rod cladding (14-1) and at two ends of the fuel pellet (12), and fuel rod end connecting pieces (10-1) are arranged at two ends of the fuel rod (2); the control rod (3) sequentially comprises a neutron absorber (17), a control rod gas gap (13-2) and a control rod cladding (14-2) from inside to outside, and control rod end connecting pieces (10-2) are arranged at two ends of the control rod (3); fuel rod gas gap (13-1) and control rod gas gap (13-2) to accommodate thermal expansion of fission gases and materials;
the upper ends and the lower ends of the fuel rods (2) and the control rods (3) are respectively positioned by an upper grid plate (8), a lower grid plate (9), fuel rod wires (15-1) wound on the fuel rod cladding (14-1) and control rod wires (15-2) wound on the control rod cladding (14-2);
the main body structures of the inner reflecting layer (7) and the outer reflecting layer (5) are made of beryllium oxide, and a plurality of reflecting layer coolant inlet channels (6) and reflecting layer coolant outlet channels (1) are respectively formed in the inner reflecting layer (7) and the outer reflecting layer (5); the reflecting layer coolant enters from the lower end of the reflecting layer coolant inlet channel (6), and after reaching the upper part of the inner reflecting layer (7), the reflecting layer coolant is baffled and flows out from the reflecting layer coolant outlet channel (1) in the outer reflecting layer (5) to play a role in cooling the reflecting layer.
2. An open grid gas-cooled space nuclear reactor core as claimed in claim 1, wherein: the coolant of the core active area (16) is helium-xenon mixed gas, flows from the lower part of the core to the upper part of the core, and is used as a heat carrier to carry away energy generated by fuel fission in the fuel rod (2).
3. An open grid gas-cooled space nuclear reactor core as claimed in claim 1, wherein: the material of the fuel pellet (12) in the fuel rod (2) is uranium dioxide, the enrichment degree is not less than 90%, and the fuel rod is of a hollow cylindrical structure.
4. An open grid gas-cooled space nuclear reactor core as claimed in claim 1, wherein: the fuel rod winding wire (15-1) and the control rod winding wire (15-2) are made of tungsten-rhenium alloy, and the fuel rod cladding (14-1) and the control rod cladding (14-2) are made of tungsten-rhenium alloy.
5. An open grid gas-cooled space nuclear reactor core as claimed in claim 1, wherein: helium is filled in the fuel rod gas gap (13-1) and the control rod gas gap (13-2).
6. An open grid gas-cooled space nuclear reactor core as claimed in claim 1, wherein: the axial reflection blocks (11) at two ends in the fuel rod (2) are made of tungsten.
7. An open grid gas-cooled space nuclear reactor core as claimed in claim 1, wherein: the neutron absorber (17) filled in the control rod (2) is made of boron carbide.
8. An open grid gas-cooled space nuclear reactor core as claimed in claim 1, wherein: the inner reflecting layer (7) and the outer reflecting layer (5) are made of beryllium oxide, and helium-xenon mixed gas is adopted as cooling agents in the inner reflecting layer (7) and the outer reflecting layer (5), and the molecular weight is 38-42 g/mol.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910509025.7A CN110232979B (en) | 2019-06-13 | 2019-06-13 | Open grid type gas-cooled space nuclear reactor core |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910509025.7A CN110232979B (en) | 2019-06-13 | 2019-06-13 | Open grid type gas-cooled space nuclear reactor core |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN110232979A CN110232979A (en) | 2019-09-13 |
| CN110232979B true CN110232979B (en) | 2020-09-01 |
Family
ID=67859806
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910509025.7A Active CN110232979B (en) | 2019-06-13 | 2019-06-13 | Open grid type gas-cooled space nuclear reactor core |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN110232979B (en) |
Families Citing this family (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110752043B (en) * | 2019-10-31 | 2023-11-24 | 华南理工大学 | Annular full-ceramic fault-tolerant accident fuel element |
| CN112951455B (en) * | 2021-02-25 | 2023-03-03 | 南华大学 | Pellet-cladding gap heat transfer improvement method based on graphene aerosol |
| CN113270205B (en) * | 2021-03-29 | 2023-12-22 | 中国核电工程有限公司 | Modularized pressure pipe type gas-cooled micro-reactor core |
| CN113270208A (en) * | 2021-03-29 | 2021-08-17 | 中国核电工程有限公司 | Modular transverse prismatic air-cooled micro-reactor core system |
| CN113270206B (en) * | 2021-03-29 | 2023-12-22 | 中国核电工程有限公司 | Small prismatic annular gas-cooled micro-reactor core system with densely arranged coolant channels |
| CN113241201B (en) * | 2021-04-29 | 2022-03-04 | 西南科技大学 | Non-uniform control rod with non-uniform reflecting layer |
| CN113192657B (en) * | 2021-04-29 | 2022-11-04 | 西南科技大学 | Non-uniform control rod with reflecting layer |
| CN113270210B (en) * | 2021-05-21 | 2022-10-25 | 西安交通大学 | Reactor core structure of lightweight heat pipe reactor with low uranium loading capacity |
| CN113436756B (en) * | 2021-06-04 | 2023-03-10 | 西安交通大学 | Compact type space reactor core structure suitable for passive start |
| CN113436757B (en) * | 2021-07-19 | 2023-01-17 | 西安交通大学 | Modular solid-state reactor core with temperature equalization structure |
| CN114334196B (en) * | 2021-12-15 | 2022-11-22 | 上海交通大学 | Intrinsic safety design method, device and equipment for helium-xenon cooled reactor |
| CN115101221B (en) * | 2022-08-05 | 2023-05-02 | 西安交通大学 | Integrated movable air-cooled miniature power reactor core |
Family Cites Families (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20070133733A1 (en) * | 2005-12-07 | 2007-06-14 | Liviu Popa-Simil | Method for developing nuclear fuel and its application |
| CN106128517B (en) * | 2016-06-24 | 2017-11-28 | 西安交通大学 | A kind of supercritical carbon dioxide using rod shape fuel component cools down rickle |
| CN106875984B (en) * | 2016-12-28 | 2018-04-10 | 中国科学院合肥物质科学研究院 | A kind of new accident fault tolerant fuel component |
| CN207731671U (en) * | 2017-12-19 | 2018-08-14 | 中国原子能科学研究院 | A kind of two-sided cooling annular fuel rod with wrapping wire |
| CN108648834B (en) * | 2018-04-19 | 2019-04-09 | 西安交通大学 | Honeycomb briquet type fuel assembly and the cooling fast reactor reactor core of small size long-life lead bismuth |
-
2019
- 2019-06-13 CN CN201910509025.7A patent/CN110232979B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| CN110232979A (en) | 2019-09-13 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN110232979B (en) | Open grid type gas-cooled space nuclear reactor core | |
| JP6000403B2 (en) | Fuel assembly | |
| US2838452A (en) | Plates with oxide inserts | |
| US20230112687A1 (en) | Integrated in-vessel neutron shield | |
| KR102152188B1 (en) | Thorium fuel based space reactor core and nuclear reactor having the same | |
| JPH0128357B2 (en) | ||
| CN113270210B (en) | Reactor core structure of lightweight heat pipe reactor with low uranium loading capacity | |
| CN109859859A (en) | It is a kind of based on the thermally conductive no heat convection integral module formula microminiature space based reactor reactor core of tungsten | |
| CN111081390B (en) | Double-clad fuel element with enhanced moderating capability | |
| US2949416A (en) | Concentric tubular fuel element | |
| CN111276265A (en) | Rod-type fuel element using uranium-yttrium hydride fuel | |
| CN112216407A (en) | High temperature gas cooled reactor and system | |
| CN109859861B (en) | Coolant-free ultra-small compact space reactor core based on carbon nano tube | |
| CN116110619A (en) | Air-cooled micro-reactor fuel assembly and air-cooled micro-reactor core system | |
| CN113436758B (en) | Radial flow high-temperature gas cooled reactor fuel assembly for space propulsion and working method | |
| CN115662659A (en) | High specific power reactor core structure of heat pipe reactor | |
| CN111341467B (en) | Metal reactor internal member suitable for spherical fuel and high-temperature coolant | |
| CA2307402C (en) | Modular fuel element adaptable to different nuclear power plants with cooling channels | |
| JP2000241582A (en) | Fuel assembly, fuel rod and reactor core | |
| CN112216408A (en) | Fuel element, high-temperature gas-cooled reactor and high-temperature gas-cooled reactor system | |
| CN113362971B (en) | Compact heat pipe reactor core structure for static conversion | |
| CN213815564U (en) | Fuel element, high-temperature gas-cooled reactor and high-temperature gas-cooled reactor system | |
| JP2002006074A (en) | Sodium cooling fast reactor | |
| CN115101221B (en) | Integrated movable air-cooled miniature power reactor core | |
| CN115101222B (en) | Reactor core structure based on graphite-based dispersion micro-encapsulated fuel |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |