CN113130099A - Compact-structure high-flux small-sized multipurpose lead-cooled fast reactor - Google Patents
Compact-structure high-flux small-sized multipurpose lead-cooled fast reactor Download PDFInfo
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- CN113130099A CN113130099A CN202110375534.2A CN202110375534A CN113130099A CN 113130099 A CN113130099 A CN 113130099A CN 202110375534 A CN202110375534 A CN 202110375534A CN 113130099 A CN113130099 A CN 113130099A
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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
- G21C3/36—Assemblies of plate-shaped fuel elements or coaxial tubes
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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
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/18—Moderator or core structure; Selection of materials for use as moderator characterised by the provision of more than one active zone
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
- G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
- G21C7/12—Means for moving control elements to desired position
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
- G21C9/027—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by fast movement of a solid, e.g. pebbles
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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
Abstract
The invention discloses a compact-structure high-flux small multipurpose lead-cooled fast reactor, which comprises an outer containment and an inner containment, wherein a cavity is formed by enclosing the outer containment and the inner containment, the middle part of the inner containment is hollow to form a flux trap, an inner fuel area and an outer fuel area which are sequentially distributed from inside to outside are arranged in the cavity, fuel assemblies are arranged in the inner fuel area and the outer fuel area, a safety plate is movably arranged between the inner fuel area and the inner containment, a plurality of adjusting plates are movably arranged between the outer containment and the outer fuel area, the adjusting plates are circumferentially arranged along the outer fuel area and can independently move, the safety plate and the adjusting plates are used for being inserted or pulled out along the axial direction of the lead-cooled fast reactor, the inner fuel area and the outer fuel area are communicated with the cavity, the cavity is used for filling coolant lead, and a reflecting layer and a shielding layer are sequentially arranged on the outer peripheral side. The lead-cooled fast reactor is beneficial to realizing miniaturization development, and has high safety performance and wide application.
Description
Technical Field
The invention relates to the technical field of nuclear engineering and nuclear, in particular to a compact-structure high-flux small multipurpose lead-cooled fast reactor.
Background
The lead-cooled fast reactor is a fast neutron reactor cooled by liquid lead or lead-bismuth alloy, can well meet the target requirements of safety, economy, continuity and nuclear non-diffusion of a fourth-generation reactor, and is the most developed reactor type of six main reactor types of the fourth-generation reactor.
The development direction of the lead-based fast reactor is mainly miniaturization, because the small reactor has the characteristics of small size, convenience, wide application and the like. The lead or lead bismuth and other coolants have good physical parameters, have the characteristics of high boiling point, high thermal conductivity, good thermal expansibility and the like, have good heat transfer performance, avoid the exposure of a reactor core caused by the boiling of the coolant, and prevent the occurrence of molten pile story; compared with other coolants, the lead or the lead bismuth is inactive in chemical property and is not easy to generate chemical reaction on other materials in the reactor core; the lead-cold fast reactor has strong natural circulation capability, so that the lead-cold fast reactor has good passive safety. These characteristics make lead-cooled fast reactors extremely promising, especially with unique advantages in the development of small modular reactors.
Most of the existing fuel assembly designs of the lead-cooled fast reactor adopt a form that a plurality of fuel rods are packaged into one fuel assembly, the structure is generally complex, and the miniaturization development of the lead-cooled fast reactor is not facilitated.
Disclosure of Invention
In order to solve the technical problems mentioned in the background technology, the invention provides a compact high-flux small multipurpose lead-cooled fast reactor.
The technical scheme adopted by the invention is as follows: a high flux small-sized multipurpose lead-cooled fast reactor with compact structure comprises an outer containment and an inner containment, the outer containment vessel and the inner containment vessel surround a formed cavity, the middle part of the inner containment vessel is hollow to form a flux trap, an inner fuel area and an outer fuel area which are distributed from inside to outside in sequence are arranged in the cavity, fuel assemblies are arranged in the inner fuel area and the outer fuel area, a safety plate is movably arranged between the inner fuel area and the inner containment, a plurality of adjusting plates are movably arranged between the outer containment and the outer fuel area, the adjusting plates are circumferentially arranged along the outer fuel area and can independently move, the safety plate and the adjusting plate are used for being inserted or pulled out along the axial direction of the lead-cooled fast reactor, the inner fuel area and the outer fuel area are both communicated with the cavity, the cavity is used for filling coolant lead, and a reflecting layer and a shielding layer are sequentially arranged on the outer periphery side of the outer containment.
The method has the following beneficial effects: the plate type fuel assembly commonly used in research reactors is applied to the lead-cooled fast reactor, so that the overall heat transfer performance of the reactor is greatly enhanced, and the miniaturization development of the lead-cooled fast reactor is facilitated; the double control system of the internal control panel and the external control panel is adopted, so that the safety performance of the reactor is guaranteed; an irradiation channel is provided for the lead-cooled fast reactor, the application of the reactor is increased, and additional economic benefits can be brought.
Further, the enrichment of the fuel uranium 235 in the inner fuel zone and the outer fuel zone is set to be different.
Furthermore, the inner fuel area is provided with 4 inner fuel area units, and the fuel assemblies in the inner fuel area units are a plurality of arc-shaped plates which are arranged at intervals from inside to outside and have an angle of 90 degrees; the outer fuel area is set into 8 outer fuel area units, and the fuel assemblies positioned in the outer fuel area units are a plurality of arc-shaped plates which are arranged at intervals from inside to outside and have an angle of 45 degrees; and cooling channels are formed among the arc-shaped plates, and the number of the adjusting plates is 8.
Furthermore, 8 guide rails are arranged on the inner side of the outer containment, guide grooves are formed in two sides of each guide rail, and the adjusting plate is arranged on the guide rails in a sliding mode.
Further, a sleeve is arranged on the outer side of the inner containment vessel, the sleeve is hollow, and the safety plate moves back and forth along the hollow part of the sleeve.
Further, the arc-shaped plate comprises a fuel cladding, the middle of the interior of the fuel cladding is filled with fuel pellets, and the two ends of each fuel pellet are sequentially and symmetrically provided with a fission air cavity and a reflection part along the axial direction.
Further, the safety plate and the adjusting plate both comprise a control plate cladding, the middle of the interior of the control plate cladding is filled with absorbing material boron carbide, and the two ends of the control plate cladding are filled with metal material tungsten.
Furthermore, a positioning grid is arranged in the chamber, the positioning grid is fixedly installed on the inner side of the outer containment vessel and the outer side of the inner containment vessel, the positioning grid comprises side plates used for separating fuel areas, and two side portions of the arc-shaped plate are fixedly connected to the side plates.
Further, both sides of the arc-shaped plate are provided with non-fuel sections, and the arc-shaped plate is connected to the side plate through the non-fuel sections.
Drawings
The invention is further illustrated with reference to the following figures and examples:
FIG. 1 is an axial sectional view of a compact high-flux small multipurpose lead-cooled fast reactor provided by an embodiment of the invention;
FIG. 2 is a radial cross-sectional view of a compact high-flux small multipurpose lead-cooled fast reactor provided by an embodiment of the invention;
FIG. 3 is a schematic radial cross-sectional view of a fuel assembly in an inner fuel zone of an embodiment of the present invention;
FIG. 4 is a schematic radial cross-sectional view of a fuel assembly in the outer fuel zone of an embodiment of the present invention;
FIG. 5 is a schematic radial cross-sectional view of an arcuate plate in the inner fuel zone of an embodiment of the present invention;
FIG. 6 is a schematic radial cross-sectional view of an arcuate plate in the outer fuel zone of an embodiment of the present invention;
FIG. 7 is an axial cross-sectional view of an arcuate plate in an embodiment of the present invention;
FIG. 8 is a schematic axial cross-sectional view of an adjustment plate and a safety plate in an embodiment of the invention;
FIG. 9 is a schematic radial cross-section of an adjustment plate according to an embodiment of the invention;
fig. 10 is a schematic radial cross-section of a security pane in an embodiment of the invention.
Description of reference numerals: 1-shielding layer, 2-reflecting layer, 3-outer containment, 4-regulating plate, 5-chamber, 6-annular fuel area, 7-safety plate, 8-inner containment, 9-flux trap, 10-inner fuel area, 11-spacer grid, 12-outer fuel area, 13-arc plate, 14-side plate, 15-cooling channel, 16-fuel cladding, 17-fuel pellet, 18-air cavity, 19-reflecting part, 20-boron carbide, 21-tungsten, 22-control plate cladding, 23-guide rail and 24-sleeve.
Detailed Description
Reference will now be made in detail to the present preferred embodiments of the present invention, examples of which are illustrated in the accompanying drawings, wherein like reference numerals refer to like elements throughout.
In the description of the present invention, it should be understood that the orientation or positional relationship referred to in the description of the orientation, such as the upper, lower, front, rear, left, right, etc., is based on the orientation or positional relationship shown in the drawings, and is only for convenience of description and simplification of description, and does not indicate or imply that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and thus, should not be construed as limiting the present invention.
In the description of the present invention, the meaning of a plurality of means is one or more, the meaning of a plurality of means is two or more, and larger, smaller, larger, etc. are understood as excluding the number, and larger, smaller, inner, etc. are understood as including the number. If the first and second are described for the purpose of distinguishing technical features, they are not to be understood as indicating or implying relative importance or implicitly indicating the number of technical features indicated or implicitly indicating the precedence of the technical features indicated.
In the description of the present invention, unless otherwise explicitly limited, terms such as arrangement, installation, connection and the like should be understood in a broad sense, and those skilled in the art can reasonably determine the specific meanings of the above terms in the present invention in combination with the specific contents of the technical solutions.
Referring to fig. 1 to 10, the embodiment of the invention provides a compact high-flux small multipurpose lead-cooled fast reactor. Since there are many types of existing fuel assemblies, in research stacks, plate-type fuel assemblies are often used as fuel assemblies, and the plate-type fuel assemblies are fixed on two side plates 14 to form a fuel assembly, and the fuel assembly has a shape of a circular ring, a sector, a regular polygon, or the like. The plate type fuel assembly has good heat transfer performance due to the sufficient contact area between the plate type fuel plate and the coolant, and the reactor core has the characteristics of small volume, high neutron flux and high power density. At present, the development direction of the lead-cooled fast reactor is mainly miniaturization, and the core of the plate type fuel assembly just meets the requirement of miniaturization.
Specifically, the compact-structure high-flux small multipurpose lead-cooled fast reactor comprises an outer containment vessel 3 and an inner containment vessel 8, wherein the outer containment vessel 3 and the inner containment vessel 8 surround a cavity 5, the middle part of the inner containment vessel 8 is hollow to form a flux trap 9, an inner fuel area 10 and an outer fuel area 12 are arranged in the cavity 5 and sequentially distributed from inside to outside, fuel assemblies are arranged in the inner fuel area 10 and the outer fuel area 12, a safety plate 7 is movably arranged between the inner fuel area 10 and the inner containment vessel 8, a plurality of adjusting plates 4 are movably arranged between the outer containment vessel 3 and the outer fuel area 12, the adjusting plates 4 are circumferentially arranged along the outer fuel area 12 and can independently move, the safety plate 7 and the adjusting plates 4 are used for being inserted or pulled out along the axial direction of the lead-cooled fast reactor, and the inner fuel area 10 and the outer fuel area 12 are both communicated with the cavity 5, the cavity 5 is used for filling coolant lead, and the outer periphery side of the outer containment 3 is sequentially provided with a reflecting layer 2 and a shielding layer 1.
Preferably, the enrichment of the fuel uranium 235 in the inner fuel zone 10 and the outer fuel zone 12 is set to be different.
Preferably, the inner fuel area 10 is provided with 4 inner fuel area units, and the fuel assemblies in the inner fuel area units are a plurality of arc-shaped plates 13 which are arranged at intervals from inside to outside and have an angle of 90 degrees; the outer fuel area 12 is set into 8 outer fuel area units, and the fuel assemblies in the outer fuel area units are a plurality of arc-shaped plates 13 which are arranged at intervals from inside to outside and have an angle of 45 degrees; cooling channels 15 are formed between the arc-shaped plates 13, and the number of the adjusting plates 4 is 8.
Preferably, 8 guide rails 23 are arranged on the inner side of the outer containment vessel 3, guide grooves are formed on two sides of each guide rail 23, and the adjusting plate 4 is slidably arranged on the guide rails 23.
Preferably, a sleeve is arranged on the outer side of the inner containment vessel 8, the sleeve is hollow, and the safety plate 7 moves back and forth along the hollow part of the sleeve.
Preferably, the arc plate 13 comprises a fuel cladding 16, the fuel cladding 16 is internally filled with fuel pellets 17, and the two ends of the fuel pellets 17 are axially and symmetrically provided with a fission air cavity 18 and a reflector 19 in sequence.
Preferably, the safety plate 7 and the adjusting plate 4 each include a control plate enclosure 22, and the control plate enclosure 22 is filled with an absorbing material, namely boron carbide 20, at the middle inside and filled with a metal material, namely tungsten 21, at both ends.
Preferably, a spacer grid 11 is arranged in the chamber 5, the spacer grid 11 is fixedly arranged on the inner side of the outer containment vessel 3 and the outer side of the inner containment vessel 8, the spacer grid 11 comprises a side plate 14 for separating the annular fuel area 6, and two side parts of the arc-shaped plate 13 are fixedly connected to the side plate 14. The two side plates 14 in the inner fuel zone 10 are arranged at 90 deg. and the two side plates 14 in the outer fuel zone 12 are arranged at 45 deg..
Preferably, both side portions of the arc plate 13 are provided with non-fuel sections, and the arc plate 13 is connected to the side plate 14 through the non-fuel sections.
Since the lead coolant has a corrosive effect on the cladding, especially when the coolant flow rate is high, an anti-corrosion coating may be added to the surface of the cladding. In some embodiments, the enclosure materials of the arc plate 13, the regulating plate 4 and the safety plate 7 are all made of T91 stainless steel.
Meanwhile, in some embodiments, the material of the reflecting layer 2 adopts a mixture of T91 steel and lead in a certain proportion; the shielding layer 1 is made of a mixture of boron carbide 20 and lead in a certain proportion.
In the embodiment, the whole structure of the high-flux small multipurpose lead-cooled fast reactor is cylindrical, is completely symmetrical in the radial direction, and generally comprises a middle irradiation region, an annular fuel region, a reflecting layer region and a shielding layer region. The middle irradiation area is a cylindrical flux trap 9, the annular fuel area 6 is divided into an inner fuel area 10 and an outer fuel area 12, 12 fuel assemblies are arranged in total, and fuels with different enrichment degrees are adopted in different fuel areas. 4 fuel assemblies are arranged in the inner fuel area 10, each fuel assembly is an 1/4 cylindrical ring, and each fuel assembly consists of an arc-shaped plate 13 with the angle of 90 degrees; the outer fuel area 12 is provided with 8 fuel assemblies, each fuel assembly is an 1/8 cylindrical ring, each fuel assembly consists of an arc plate 13 with the angle of 45 degrees, the middle of the arc plate 13 is provided with a fuel pellet 17, and the two ends of the arc plate are symmetrically provided with a fission air cavity 18 and a reflecting part 19. The curved plates 13 are fixed to the spacer grid 11, and the gaps between the curved plates 13 are cooling channels 15.
The safety plate 7 is a hollow cylinder, and a sleeve is arranged outside the inner safety shell 8 to guide the safety plate 7 to be rapidly inserted into the core in emergency shutdown. The safety plate 7 is in the extracted state in normal operation, and the space is filled with coolant. The adjusting plate 4 is correspondingly arranged in an arc shape and can move up and down independently, the space left after moving is filled with coolant, eight vertical guide grooves are uniformly arranged on the inner wall side of the outer containment vessel 3 along the circumferential direction to allow the adjusting plate 4 to move up and down, and the gap between the adjusting plate 4 and the outer containment vessel 3 is filled with coolant.
The invention provides a lead-cooled fast reactor core structure with good safety performance, compact structure and multiple purposes. Firstly, in the aspect of safety performance, the invention adopts a double-control system, one is an adjusting plate 4 for adjusting the reactivity, and the reactivity of the reactor can be adjusted by changing the insertion depth of the adjusting plate 4; the other is a safety plate 7 for emergency shutdown, when an emergency occurs, the safety plate 7 can be quickly inserted into a reactor core to stop the reactor, and the two systems can independently regulate and shut down the reactor, so that the safety of the reactor is ensured. Secondly, the fuel zone division setting is adopted, and the enrichment degrees of the fuel uranium 235 of the inner zone and the outer zone are different, so that the flattening of the power in the reactor is facilitated. The fuel assembly adopts the plate fuel assembly, the plate fuel has better heat transfer capability and radiation swelling resistance compared with rod fuel, and the heat transfer capability of the coolant lead is better than that of water, so that the heat transfer capability of the reactor is greatly increased, and the reactor core of the reactor can be made smaller and more compact. Finally, the core intermediate flux trap 9 of the present invention is a high neutron flux region that provides an irradiation channel for irradiation testing. Since the nuclear reaction rate of the target placed in the irradiation channel is proportional to the number of neutrons absorbed in unit time, the higher the neutron flux of the reactor, the better the neutron flux, and the high neutron flux provided by the intermediate flux trap 9, which is set as the irradiation channel, is fully utilized to complete an experiment in a short time.
Therefore, the invention not only can be used as a power reactor to output heat energy, but also can be used as a research reactor to carry out fuel element irradiation test, material irradiation test, monocrystalline silicon neutron transmutation doping research and preparation and the like. The lead-cooled fast reactor with the structure has good safety performance, compact structure and wide application field, in particular to the future advanced industrial field.
In some embodiments, since the density of the coolant lead is high, the buoyancy generated to the safety plate 7 or the adjusting plate 4 when it is inserted into the core is also high, and thus the load-bearing material tungsten 21 is added to the upper and lower portions of the safety plate 7 or the adjusting plate 4.
The invention has the advantages that: the plate type fuel assembly commonly used in research reactors is applied to the lead-cooled fast reactor, so that the overall heat transfer performance of the reactor is greatly enhanced, and the miniaturization development of the lead-cooled fast reactor is facilitated; the double control system of the internal control panel and the external control panel is adopted, so that the safety performance of the reactor is guaranteed; an irradiation channel is provided for the lead-cooled fast reactor, the application of the reactor is increased, and additional economic benefits can be brought.
By taking the design of the reactor core applied to the advanced industrial nuclear reactor as an example, the compact-structure high-flux small multipurpose lead-cooled fast reactor provided by the invention can provide heat energy required by production and meet the power demand on one hand, and can utilize an irradiation channel to perform research such as material test and the like on the other hand, so that additional benefits can be brought.
While the embodiments of the present invention have been described in detail with reference to the drawings, the present invention is not limited to the above embodiments, and various changes can be made without departing from the spirit of the present invention within the knowledge of those skilled in the art.
Claims (9)
1. A high-flux small multipurpose lead-cooled fast reactor with a compact structure is characterized by comprising an outer containment and an inner containment, wherein the outer containment and the inner containment are surrounded to form a cavity, the middle of the inner containment is hollow to form a flux trap, an inner fuel area and an outer fuel area which are sequentially distributed from inside to outside are arranged in the cavity, fuel assemblies are arranged in the inner fuel area and the outer fuel area, a safety plate is movably arranged between the inner fuel area and the inner containment, a plurality of adjusting plates are movably arranged between the outer containment and the outer fuel area, the adjusting plates are circumferentially arranged along the outer fuel area and can independently move, the safety plate and the adjusting plates are used for being inserted or pulled out along the axial direction of the lead-cooled fast reactor, the inner fuel area and the outer fuel area are communicated with the cavity, and the cavity is used for filling coolant lead, and the outer peripheral side of the outer containment is sequentially provided with a reflecting layer and a shielding layer.
2. The compact high-flux small multipurpose lead-cooled fast reactor as claimed in claim 1, wherein: the enrichment of the fuel uranium 235 in the inner fuel zone and the outer fuel zone is set to be different.
3. The compact high-flux small multipurpose lead-cooled fast reactor as claimed in claim 1, wherein: the inner fuel area is set into 4 inner fuel area units, and the fuel assemblies in the inner fuel area units are a plurality of arc-shaped plates which are arranged at intervals from inside to outside and have an angle of 90 degrees; the outer fuel area is set into 8 outer fuel area units, and the fuel assemblies positioned in the outer fuel area units are a plurality of arc-shaped plates which are arranged at intervals from inside to outside and have an angle of 45 degrees; and cooling channels are formed among the arc-shaped plates, and the number of the adjusting plates is 8.
4. The compact high-flux small multipurpose lead-cooled fast reactor of claim 3, wherein: the inner side of the outer containment is provided with 8 guide rails, two sides of each guide rail are provided with guide grooves, and the adjusting plate is arranged on the guide rails in a sliding mode.
5. The compact high-flux small multipurpose lead-cooled fast reactor of claim 3, wherein: the safety device comprises an inner safety shell, a safety plate and a sleeve, wherein the sleeve is arranged on the outer side of the inner safety shell and is hollow, and the safety plate moves back and forth along the hollow part of the sleeve.
6. The compact high-flux small multipurpose lead-cooled fast reactor of claim 3, wherein: the arc-shaped plate comprises a fuel cladding, the middle of the interior of the fuel cladding is filled with fuel pellets, and the two ends of each fuel pellet are sequentially and symmetrically provided with a fission air cavity and a reflection part along the axial direction.
7. The compact high-flux small multipurpose lead-cooled fast reactor of claim 3, wherein: the safety plate and the adjusting plate respectively comprise a control plate cladding, the middle of the interior of the control plate cladding is filled with absorption material boron carbide, and the two ends of the control plate cladding are filled with metal material tungsten.
8. The compact high-flux small multipurpose lead-cooled fast reactor of claim 3, wherein: and a positioning grid is arranged in the chamber, the positioning grid is fixedly arranged on the inner side of the outer containment and the outer side of the inner containment, the positioning grid comprises side plates for separating fuel areas, and two side parts of the arc-shaped plate are fixedly connected to the side plates.
9. The compact high-flux small multipurpose lead-cooled fast reactor as claimed in claim 8, wherein: both sides portion of arc all is provided with non-fuel section, the arc is connected to on the curb plate through non-fuel section.
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| CN202110375534.2A CN113130099A (en) | 2021-04-08 | 2021-04-08 | Compact-structure high-flux small-sized multipurpose lead-cooled fast reactor |
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| CN202110375534.2A CN113130099A (en) | 2021-04-08 | 2021-04-08 | Compact-structure high-flux small-sized multipurpose lead-cooled fast reactor |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114267461A (en) * | 2021-12-24 | 2022-04-01 | 西安交通大学 | Plate-shaped fuel assembly enhanced heat exchange device |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114267461A (en) * | 2021-12-24 | 2022-04-01 | 西安交通大学 | Plate-shaped fuel assembly enhanced heat exchange device |
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