CN110853777A - Fuel assembly structure for enhancing negative feedback of temperature of gas-cooled fast reactor and reactor core structure - Google Patents
Fuel assembly structure for enhancing negative feedback of temperature of gas-cooled fast reactor and reactor core structure Download PDFInfo
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- CN110853777A CN110853777A CN201911084139.8A CN201911084139A CN110853777A CN 110853777 A CN110853777 A CN 110853777A CN 201911084139 A CN201911084139 A CN 201911084139A CN 110853777 A CN110853777 A CN 110853777A
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- 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
- G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
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- 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
- G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
- G21C15/06—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material in fuel elements
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- 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
- G21C15/24—Promoting flow of the coolant
- G21C15/253—Promoting flow of the coolant for gases, e.g. blowers
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/322—Means to influence the coolant flow through or around the bundles
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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
- Y02E30/30—Nuclear fission reactors
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
A fuel assembly structure and reactor core structure for enhancing the negative feedback of the temperature of a gas-cooled fast reactor, the fuel assembly is radially divided into three regions, namely an active region, a moderation region and an assembly box from inside to outside; the reactor core is radially arranged and divided into an inner fuel area and an outer fuel area according to different arrangement components, and a special coolant flow channel and a radial reflecting layer are arranged outside the fuel areas; the fuel area is axially arranged and comprises a lower reflecting layer, a fuel layer, an air cavity and an upper reflecting layer from bottom to top; the fuel layer of the inner fuel area is axially subdivided into three layers, fuel is arranged at two ends, and a section of lean uranium is arranged in the middle; the coolant flow adopts a double-flow-path design, and the inlet coolant flows downwards from the fuel area and then flows upwards from a special coolant flow channel outside the stack; the structure can effectively enhance the temperature negative feedback of the gas-cooled fast reactor and improve the inherent safety of the gas-cooled reactor.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor engineering, and particularly relates to a structure for enhancing the temperature negative feedback of a gas-cooled fast reactor.
Background
Common cooling agents for the gas-cooled fast reactor include helium, helium-xenon mixed gas and the like. Compared with the existing pebble bed type high-temperature gas cooled reactor, the gas cooled fast reactor can realize higher power density and effectively reduce the volume of a reactor core. Meanwhile, the gas working medium cooling cycle adopts Brayton cycle, so that the cycle efficiency is higher; the whole process has no phase change, a steam generator, a voltage stabilizer, a steam-water separator and a dryer used in a pressurized water reactor are not needed, the structure is compact, and the volume and the weight of a thermodynamic system are greatly reduced.
Based on the advantages of the gas-cooled fast reactor, the method is expected to be applied to the design of a nuclear power system with higher requirements on volume and weight. Safety is one of the most important considerations for such reactors, and it should be considered that the core design is important, and improving the intrinsic safety of the reactor is the most effective means for enhancing safety. But the moderation ability of the gas coolant to neutrons is weak, the energy spectrum of the reactor core is hard, and the fuel Doppler negative feedback effect of the reactor is not strong; meanwhile, the gas density is small, the reaction section with neutrons is small, and the feedback effect caused by gas expansion is weak when the temperature rises; making the temperature negative feedback of the core as a whole much weaker than other reactor types presents significant safety challenges.
Disclosure of Invention
In order to solve the problems, the invention provides a structure for enhancing the temperature negative feedback of the gas-cooled fast reactor, which strengthens the temperature negative feedback effect of the reactor through reasonable component design and reactor core fuel arrangement, so that the reactor core obtains enough inherent safety.
In order to achieve the purpose, the invention adopts the following technical scheme:
a fuel assembly structure for enhancing the negative temperature feedback of a gas-cooled fast reactor is in a regular hexagon shape, is divided into three regions from inside to outside, and sequentially comprises an active region 1, a moderation region 2 and an assembly box 3; the active region 1 is composed of 91 fuel rods and coolant outside the fuel rods.
The material of the slowing-down zone 2 is ZrHx。
The fuel rod consists of a central air hole 4, fuel 5, an air gap 6 and a cladding 7 from inside to outside in sequence.
The material of the fuel 5 is UO2And (3) fuel.
The material of the cladding 7 is austenitic stainless steel.
A core structure for enhancing the negative temperature feedback of a gas-cooled fast reactor is characterized in that the core comprises an inner fuel area 8, an outer fuel area 9, a special coolant channel 11 and a radial reflecting layer 12 from inside to outside in the radial direction; 19 control component channels 10 are reserved in the inner fuel area 8 and the outer fuel area 9; the coolant flows downwards from the inner fuel area 8 and the outer fuel area 9 and flows upwards from the special coolant channel 11;
the axial structure of the components of the inner fuel area 8 is sequentially an upper reflecting layer 13, an air cavity layer 14, an upper fuel section 15, a depleted uranium layer 16, a lower fuel section 17 and a lower reflecting layer 18 from top to bottom; the axial structure of the components of the outer fuel zone 9 is sequentially an upper reflecting layer 13, an air cavity layer 14, a fuel section 19 and a lower reflecting layer 18 from top to bottom; the structures of the upper fuel section 15, the depleted uranium layer 16 and the lower fuel section 17 of the inner fuel zone 8 and the fuel section 19 of the outer fuel zone 9 adopt the structure of the fuel assembly for enhancing the negative feedback of the temperature of the air-cooled fast reactor according to claim 1.
The components of the inner fuel region 8 are arranged at the 2 nd to 6 th circles in the radial direction of the core; the components of the outer fuel region 9 are arranged at the 7 th to 10 th circles in the radial direction of the core; the reserved 19 control assembly channels 10 are coolant channels and are uniformly distributed on the 1 st circle, the 4 th circle and the 7 th circle of the reactor core in the radial direction; the special coolant channel 11 is the radial 11 th circle of the reactor core; the radial reflecting layer 12 is the 12 th radial circle of the core.
The material of the radial reflecting layer 12 is stainless steel.
Compared with the prior art, the invention has the following advantages:
1. compared with the fuel assembly of the traditional gas-cooled fast reactor, the design of the moderating region 2 is added in the fuel assembly, the neutron energy spectrum can be properly softened, the average neutron energy in the reactor core is reduced, the Doppler effect of the fuel is effectively improved, and the temperature negative feedback effect brought by the Doppler effect of the fuel is enhanced;
2. compared with the fuel arrangement of the traditional gas-cooled fast reactor, the radial depleted uranium layer 16 is arranged in the active region of the fuel assembly of the inner fuel region 8, the Doppler effect of depleted uranium is stronger than that of fuel, more neutrons can be absorbed when the temperature of the reactor rises, and the temperature negative feedback caused by the whole Doppler effect of the reactor can be enhanced;
3. compared with the core arrangement of the traditional gas-cooled fast reactor, the special coolant channel 11 is additionally arranged in the reflecting layer 12, the coolant flows out of the core after being heated in the fuel area, the coolant can be synchronously heated when the reactor is heated, the density is reduced, the neutron leakage rate can be effectively improved, the effective multiplication factor of neutrons in the reactor is reduced, and the temperature negative feedback caused by density expansion of the coolant is enhanced.
Drawings
FIG. 1 is a schematic cross-sectional view of a fuel assembly structure for enhancing negative feedback of temperature of an air-cooled fast reactor according to the present invention.
FIG. 2 is a schematic cross-sectional view of a fuel rod.
FIG. 3 is a schematic diagram of the radial arrangement of the core structure for enhancing the negative feedback of the temperature of the gas-cooled fast reactor.
FIG. 4 is a schematic longitudinal cross-sectional view of the assembly of the fuel zone, wherein FIG. 4a is a schematic longitudinal cross-sectional view of the assembly of the inner fuel zone and FIG. 4b is a schematic longitudinal cross-sectional view of the assembly of the outer fuel zone.
Detailed Description
The structure of the invention will be described in detail with reference to the accompanying drawings and specific embodiments.
As shown in fig. 1, a fuel assembly structure for enhancing negative temperature feedback of a gas-cooled fast reactor, the fuel assembly is hexagonal, is divided into three regions from inside to outside, and sequentially comprises an active region 1, a moderation region 2 and an assembly box 3; the active region 1 is composed of 91 fuel rods and coolant outside the fuel rods.
Preferably, the material of the moderating zone 2 is ZrHx。
Preferably, the material of the pack case 3 is stainless steel.
As shown in fig. 2, the fuel rod is composed of a central air hole 4, fuel 5, an air gap 6 and a cladding 7 in this order from the inside to the outside.
The preferred material for fuel 5 is UO2And (3) fuel.
Preferably the material of the cladding 7 is austenitic stainless steel.
As shown in fig. 3, the core structure for enhancing the temperature negative feedback of the gas-cooled fast reactor of the invention comprises an inner fuel region 8, an outer fuel region 9, a special coolant channel 11 and a radial reflecting layer 12 from inside to outside in the radial direction; 19 control component channels 10 are reserved in the inner fuel area 8 and the outer fuel area 9; the coolant flows downward from the inner fuel region 8 and the outer fuel region 9 and flows upward from the dedicated coolant passages 11.
As shown in fig. 4a of fig. 4, the axial structure of the components of the inner fuel region 8 is, from top to bottom, an upper reflector layer 13, an air cavity layer 14, an upper fuel section 15, a depleted uranium layer 16, a lower fuel section 17 and a lower reflector layer 18; as shown in fig. 3, the assemblies of the inner fuel region 8 are arranged in the second to sixth turns in the core radial direction.
As shown in fig. 4b of fig. 4, the axial structure of the components of the outer fuel region 9 is, from top to bottom, an upper reflective layer 13, an air cavity layer 14, a fuel section 19 and a lower reflective layer 18; as shown in fig. 3, the components of the outer fuel region 9 are arranged in the 7 th to 10 th turns in the core radial direction.
As shown in fig. 3, the reserved 19 control assembly channels 10 are coolant channels and are uniformly distributed on the 1 st, 4 th and 7 th circles in the radial direction of the core.
As shown in fig. 3, the dedicated coolant channel 11 is the tenth turn in the core radial direction; the radial reflecting layer 12 is the 12 th radial circle of the core.
Preferably, the material used for the radially reflective layer 12 is stainless steel.
Claims (8)
1. A fuel assembly structure for enhancing the negative temperature feedback of a gas-cooled fast reactor is characterized in that the fuel assembly is in a regular hexagon shape, is divided into three regions from inside to outside, and sequentially comprises an active region (1), a moderation region (2) and an assembly box (3); the active zone (1) is composed of 91 fuel rods and a coolant outside the fuel rods.
2. The fuel assembly for enhancing the negative feedback of the temperature of the air-cooled fast reactor according to claim 1, wherein: the above-mentionedThe material of the slowing-down zone (2) is ZrHx。
3. The structure of the fuel assembly for enhancing the negative feedback of the temperature of the air-cooled fast reactor according to claim 1, wherein: the fuel rod consists of a central air hole (4), fuel (5), an air gap (6) and a cladding (7) from inside to outside in sequence.
4. The structure of the fuel assembly for enhancing the negative feedback of the temperature of the air-cooled fast reactor according to claim 3, wherein: the material of the fuel (5) is UO2And (3) fuel.
5. The structure of the fuel assembly for enhancing the negative feedback of the temperature of the air-cooled fast reactor according to claim 3, wherein: the material of the cladding (7) is austenitic stainless steel.
6. A core structure for enhancing the negative feedback of the temperature of a gas-cooled fast reactor is characterized in that: the reactor core is characterized in that an inner fuel area (8), an outer fuel area (9), a special coolant channel (11) and a radial reflecting layer (12) are respectively arranged from inside to outside in the radial direction; 19 control component channels (10) are reserved in the inner fuel area (8) and the outer fuel area (9); the coolant flows downwards from the inner fuel area (8) and the outer fuel area (9) and flows upwards from the special coolant channel (11);
the axial structure of the assembly of the inner fuel area (8) is sequentially an upper reflecting layer (13), an air cavity layer (14), an upper fuel section (15), a depleted uranium layer (16), a lower fuel section (17) and a lower reflecting layer (18) from top to bottom; the axial structure of the components of the outer fuel area (9) is sequentially an upper reflecting layer (13), an air cavity layer (14), a fuel section (19) and a lower reflecting layer (18) from top to bottom; the structures of the upper fuel section (15), the depleted uranium layer (16) and the lower fuel section (17) of the inner fuel area (8) and the fuel section (19) of the outer fuel area (9) adopt the fuel assembly structure for enhancing the negative feedback of the temperature of the air-cooled fast reactor as claimed in claim 1.
7. The core structure for enhancing the temperature negative feedback of the gas-cooled fast reactor as claimed in claim 6, wherein: the assembly of the inner fuel zone (8) is arranged in the 2 nd to 6 th circles of the core radial direction; the assembly of the outer fuel region (9) is arranged on the 7 th to 10 th circles in the radial direction of the core; the reserved 19 control assembly channels (10) are coolant channels and are uniformly distributed on the 1 st circle, the 4 th circle and the 7 th circle of the reactor core in the radial direction; the special coolant channel (11) is the 11 th radial circle of the reactor core; the radial reflecting layer (12) is the 12 th circle in the radial direction of the reactor core.
8. The core structure for enhancing the temperature negative feedback of the gas-cooled fast reactor as claimed in claim 6, wherein: the radial reflecting layer (12) is made of stainless steel.
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| Application Number | Priority Date | Filing Date | Title |
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| CN201911084139.8A CN110853777A (en) | 2019-11-07 | 2019-11-07 | Fuel assembly structure for enhancing negative feedback of temperature of gas-cooled fast reactor and reactor core structure |
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| Application Number | Priority Date | Filing Date | Title |
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| CN201911084139.8A CN110853777A (en) | 2019-11-07 | 2019-11-07 | Fuel assembly structure for enhancing negative feedback of temperature of gas-cooled fast reactor and reactor core structure |
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112669999A (en) * | 2020-12-23 | 2021-04-16 | 南京航空航天大学 | Liquid-solid dual fuel space nuclear reactor power supply |
| CN113270206A (en) * | 2021-03-29 | 2021-08-17 | 中国核电工程有限公司 | Small-sized prismatic annular gas-cooled micro-reactor core system with densely arranged coolant channels |
| CN113674877A (en) * | 2021-07-15 | 2021-11-19 | 中国核动力研究设计院 | Lead-based fast reactor magnesium oxide reflecting layer assembly and lead-bismuth fast spectrum reactor core arrangement |
| CN113793701A (en) * | 2021-08-25 | 2021-12-14 | 西安交通大学 | Spiral cross-shaped metal fuel element reactor core |
| CN113806941A (en) * | 2021-09-22 | 2021-12-17 | 上海核星核电科技有限公司 | Pressurized water reactor burnup tracking calculation method with xenon transient simulation capability |
| CN115101221A (en) * | 2022-08-05 | 2022-09-23 | 西安交通大学 | Integrated movable air-cooled miniature power reactor core |
| WO2022206064A1 (en) * | 2021-03-29 | 2022-10-06 | 中国核电工程有限公司 | Reactor core system and gas-cooled micro reactor |
Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0720765B1 (en) * | 1993-09-22 | 1997-11-19 | Siemens Aktiengesellschaft | Fuel element with a shortened supporting coolant pipe |
| CN102737735A (en) * | 2012-07-04 | 2012-10-17 | 中国核动力研究设计院 | Combined square fuel assembly, reactor core and two-pass flowing method of super-critical water reactor |
| CN105976879A (en) * | 2016-05-09 | 2016-09-28 | 中国科学院上海应用物理研究所 | Assembly type molten salt reactor |
| CN106128517A (en) * | 2016-06-24 | 2016-11-16 | 西安交通大学 | A kind of supercritical carbon dioxide cooling rickle using rod shape fuel assembly |
| US20180190394A1 (en) * | 2016-12-30 | 2018-07-05 | Korea Advanced Institute Of Science And Technology | Nuclear fuel assembly for a thermal neutron reactor |
| CN109273105A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | A kind of supercritical carbon dioxide reactor fuel assemblies |
| CN110060788A (en) * | 2019-04-10 | 2019-07-26 | 西安交通大学 | A kind of general thermion nuclear reactor for space power supply thermal transient Analysis of Electrical Characteristics method |
| CN110073443A (en) * | 2016-12-22 | 2019-07-30 | 泰拉能源公司 | Dependent response control in fission-type reactor |
| CN110289109A (en) * | 2019-07-08 | 2019-09-27 | 西安交通大学 | The cooling similar honeycomb briquet type fuel assembly of liquid chlorate and the reactor core using the component |
-
2019
- 2019-11-07 CN CN201911084139.8A patent/CN110853777A/en active Pending
Patent Citations (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0720765B1 (en) * | 1993-09-22 | 1997-11-19 | Siemens Aktiengesellschaft | Fuel element with a shortened supporting coolant pipe |
| CN102737735A (en) * | 2012-07-04 | 2012-10-17 | 中国核动力研究设计院 | Combined square fuel assembly, reactor core and two-pass flowing method of super-critical water reactor |
| CN105976879A (en) * | 2016-05-09 | 2016-09-28 | 中国科学院上海应用物理研究所 | Assembly type molten salt reactor |
| CN106128517A (en) * | 2016-06-24 | 2016-11-16 | 西安交通大学 | A kind of supercritical carbon dioxide cooling rickle using rod shape fuel assembly |
| CN110073443A (en) * | 2016-12-22 | 2019-07-30 | 泰拉能源公司 | Dependent response control in fission-type reactor |
| US20180190394A1 (en) * | 2016-12-30 | 2018-07-05 | Korea Advanced Institute Of Science And Technology | Nuclear fuel assembly for a thermal neutron reactor |
| CN109273105A (en) * | 2018-09-13 | 2019-01-25 | 中国核动力研究设计院 | A kind of supercritical carbon dioxide reactor fuel assemblies |
| CN110060788A (en) * | 2019-04-10 | 2019-07-26 | 西安交通大学 | A kind of general thermion nuclear reactor for space power supply thermal transient Analysis of Electrical Characteristics method |
| CN110289109A (en) * | 2019-07-08 | 2019-09-27 | 西安交通大学 | The cooling similar honeycomb briquet type fuel assembly of liquid chlorate and the reactor core using the component |
Non-Patent Citations (2)
| Title |
|---|
| 郑友琦: "超临界水冷堆可燃毒物设计与分析", 《原子能科学技术》 * |
| 郑友琦: "超临界水冷堆环形燃料组件核热耦合分析", 《原子能科学技术》 * |
Cited By (12)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112669999A (en) * | 2020-12-23 | 2021-04-16 | 南京航空航天大学 | Liquid-solid dual fuel space nuclear reactor power supply |
| CN112669999B (en) * | 2020-12-23 | 2024-05-17 | 南京航空航天大学 | Liquid-solid dual fuel space nuclear reactor power supply |
| CN113270206A (en) * | 2021-03-29 | 2021-08-17 | 中国核电工程有限公司 | Small-sized prismatic annular gas-cooled micro-reactor core system with densely arranged coolant channels |
| WO2022206064A1 (en) * | 2021-03-29 | 2022-10-06 | 中国核电工程有限公司 | Reactor core system and gas-cooled micro reactor |
| 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 |
| CN113674877A (en) * | 2021-07-15 | 2021-11-19 | 中国核动力研究设计院 | Lead-based fast reactor magnesium oxide reflecting layer assembly and lead-bismuth fast spectrum reactor core arrangement |
| CN113793701A (en) * | 2021-08-25 | 2021-12-14 | 西安交通大学 | Spiral cross-shaped metal fuel element reactor core |
| CN113793701B (en) * | 2021-08-25 | 2022-12-09 | 西安交通大学 | Spiral cross-shaped metal fuel element reactor core |
| CN113806941A (en) * | 2021-09-22 | 2021-12-17 | 上海核星核电科技有限公司 | Pressurized water reactor burnup tracking calculation method with xenon transient simulation capability |
| CN113806941B (en) * | 2021-09-22 | 2024-01-05 | 上海核星核电科技有限公司 | Pressurized water reactor fuel consumption tracking calculation method with xenon transient simulation capability |
| CN115101221A (en) * | 2022-08-05 | 2022-09-23 | 西安交通大学 | Integrated movable air-cooled miniature power reactor core |
| CN115101221B (en) * | 2022-08-05 | 2023-05-02 | 西安交通大学 | Integrated movable air-cooled miniature power reactor core |
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Application publication date: 20200228 |