CN115101221A - Integrated movable air-cooled miniature power reactor core - Google Patents
Integrated movable air-cooled miniature power reactor core Download PDFInfo
- Publication number
- CN115101221A CN115101221A CN202210937620.2A CN202210937620A CN115101221A CN 115101221 A CN115101221 A CN 115101221A CN 202210937620 A CN202210937620 A CN 202210937620A CN 115101221 A CN115101221 A CN 115101221A
- Authority
- CN
- China
- Prior art keywords
- fuel
- reactor core
- assembly
- area
- beryllium oxide
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/04—Thermal reactors ; Epithermal reactors
- G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
- G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
- G21C1/10—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
- G21C1/12—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
-
- 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
- G21C3/42—Selection of substances for use as reactor fuel
- G21C3/58—Solid reactor fuel Pellets made of fissile material
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
-
- 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
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
An integrated movable gas-cooled miniature power reactor core is composed of a fuel area, a control rotary drum, an emergency shutdown safety device, a radial reflecting layer and an axial reflecting layer; the fuel area is formed by beryllium oxide matrix fuel assemblies and yttrium hydride matrix fuel assemblies which are closely arranged according to regular hexagon grid array rings and partitions, flow channels with different sizes and columnar fuel areas in the fuel area are arranged in a staggered partition mode according to the service life of a reactor core and the heat exchange requirement, and the columnar fuel areas all adopt accident fault-tolerant spherical TRISO granular fuel based on uranium carbide; the control rotary drum consists of an arc absorber and a control rotary drum base body, is arranged in the radial reflecting layer and is close to the outermost layer assembly of the fuel zone; the emergency shutdown safety device consists of an emergency shutdown plate and a shutdown plate chute and is embedded at the connection part of the reactor core fuel region and the radial reflecting layer; the reactor core design scheme provided by the invention has the characteristics of compact structure, high safety and convenience in transportation, and can be used for multi-scene power supply of high-power weapons, remote bases, disaster area rescue and the like.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor engineering, and particularly relates to an integrated movable type air-cooled miniature power reactor core.
Background
The movable gas-cooled micro power reactor generally refers to a movable power reactor which adopts pure helium, helium-xenon mixed gas or supercritical carbon dioxide as a coolant working medium and outputs electric power less than 10MW, and can be applied to a plurality of scenes such as remote bases, high-power weapons, disaster area rescue power supply and the like. Gas cooled micro power reactors typically use a gaseous coolant working fluid based on the brayton cycle to carry heat away from the core and to rotate a turbine to generate electricity. Although the thermal efficiency is high, the normal operating temperature is also very high. Considering that the gas heat exchange performance is limited, the design generally adopts a larger heat exchange area and selects moderator materials with excellent temperature resistance, such as graphite and the like. However, graphite has poor neutron moderating capability and is loose and porous, which often results in an excessively large core volume and a small amount of radioactive substances entering the coolant working medium, thereby affecting the mobility and safety of the reactor.
Currently, a typical representative of the internationally designed mobile gas-cooled micro-power reactors is the graphite moderator-based "Holos" reactor scheme designed by the university of Maryland, USA, whose core volume has reached 6.9m only under a single set of shutdown system design 3 . In addition, two sets of reactor shutdown systems which operate independently are generally needed in the reactor design to ensure the safety of the reactor, and the extra system space undoubtedly brings greater challenges to the maneuverability of the reactor. In addition, to flatten the core power distribution to reduce the power peak factor, current reactor designs often employ fuels of different enrichments, which in turn places a burden on the nuclear fuel manufacturing process.
Disclosure of Invention
In order to solve the problems, the invention provides an integrated movable type gas-cooled micro power reactor core, the thermal power of which is 3MW, and the reactor core can continuously run at full power for 6 years under the condition of no material change. The reactor core has the characteristics of small volume, strong maneuverability, good safety and relatively low difficulty in manufacturing nuclear fuel.
In order to achieve the purpose, the invention adopts the following technical scheme:
an integrated movable air-cooled miniature power reactor core is composed of a fuel area, a control rotary drum, an emergency shutdown safety device, a radial reflecting layer 7 and an axial reflecting layer 8 from inside to outside in sequence; the fuel area is arranged in the center of the reactor core and is formed by tightly arranging a beryllium oxide matrix fuel assembly 1 and a yttrium hydride matrix fuel assembly 2 in a regular hexagonal grid array, the beryllium oxide matrix fuel assembly 1 is arranged on the inner ring of the fuel area, and the yttrium hydride matrix fuel assembly 2 is arranged on the outer ring of the fuel area; the control rotary drum is composed of an arc absorber 3 and a control rotary drum base body 4, the arc absorber 3 is tightly attached to the control rotary drum base body 4, and the whole control rotary drum is arranged in a radial reflecting layer 7 and is close to the outermost layer of the fuel zone; the emergency shutdown safety device consists of an emergency shutdown plate 5 and a shutdown plate chute 6, wherein the shutdown plate chute 6 is arranged at the joint of the fuel area and the radial reflecting layer 7 and axially penetrates through the radial reflecting layer 7 and the axial reflecting layer 8, the emergency shutdown plate 5 is arranged in the shutdown plate chute 6, and when a safety accident occurs to the reactor core, the emergency shutdown plate can be radially inserted into the fuel area along the shutdown plate chute 6 to realize emergency shutdown of the reactor; the radial reflection layer 7 is close to the radial outermost layer of the fuel area, and the axial reflection layer 8 is tightly connected to the axial two ends of the fuel area.
The beryllium oxide matrix fuel assembly 1 and the yttrium hydride matrix fuel assembly 2 are both in a regular hexagon shape and comprise an assembly cladding 15 and a moderator matrix 16 distributed in the assembly cladding 15, 1 central columnar fuel area 10, 6 assembly inner flow channels 11 and 6 edge columnar fuel areas 12 are sequentially arranged in the assembly cladding 15 from inside to outside, and 6 edge central flow channels 13 and 6 corner flow channels 14 are arranged at the outer periphery of the assembly cladding 15 at intervals; the moderator base body 16 of the beryllium oxide base fuel assembly 1 is made of beryllium oxide material, and the moderator base body 16 of the yttrium hydride base fuel assembly 2 is made of yttrium hydride material; the component cladding 15 material is a Mo-14Re alloy.
The central columnar fuel area 10 and the edge columnar fuel area 12 are composed of spherical TRISO granular fuel which is randomly and uniformly dispersed in a graphite matrix 23 and has the enrichment degree of 19.75%; the spherical TRISO granular fuel is sequentially a uranium carbide fuel particle inner core 18, a loose pyrolytic carbon layer 19, an inner compact pyrolytic carbon layer 20, a silicon carbide layer 21 and an outer compact pyrolytic carbon layer 22 from inside to outside, wherein the radius of the uranium carbide fuel particle inner core 18 is 0.275mm, the thickness of the loose pyrolytic carbon layer 19 is 0.07mm, the thickness of the inner compact pyrolytic carbon layer 20 is 0.04mm, the thickness of the silicon carbide layer 21 is 0.035mm, and the thickness of the outer compact pyrolytic carbon layer 22 is 0.04 mm.
The radius of the central columnar fuel area 10 is 0.9cm, the radius of the flow channel 11 in the assembly is 0.45cm, the radius of the edge columnar fuel area 12 is 0.7cm, the radius of the edge central flow channel 13 is 0.6cm, the radius of the corner flow channel 14 is 0.35cm, and the thickness of the assembly cladding 15 is 0.5 mm; the pair distance of the beryllium oxide substrate fuel assembly 1 and the yttrium hydride substrate fuel assembly 2 is 6cm, and the height of the beryllium oxide substrate fuel assembly and the yttrium hydride substrate fuel assembly is 1.2 m.
The number of beryllium oxide matrix fuel assemblies 1 in the fuel area is 37, and the number of yttrium hydride matrix fuel assemblies 2 in the fuel area is 72; the beryllium oxide base fuel assembly 1 and the yttrium hydride base fuel assembly 2 in the fuel area are arranged for 7 circles from inside to outside in the radial direction, the beryllium oxide base fuel assembly 1 is arranged in the first 3 circles and the beryllium oxide base fuel assembly 5 is arranged in the 5 th circle, and the yttrium hydride base fuel assembly 2 is arranged in the 4 th circle, the 6 th circle and the 7 th circle.
The control rotary drum base body 4 is made of beryllium oxide and has an outer diameter of 9cm, and the arc absorber 3 is made of boron carbide with a boron-10 enrichment degree of 92% and has a thickness of 2 cm.
The emergency shutdown reactor plate 5 is made of boron carbide with the boron-10 enrichment degree of 92%, the whole shape is a cuboid, and semicircular drag reduction flow passages 17 which are arranged at equal intervals are arranged on the surfaces of two sides of the emergency shutdown reactor plate, which are close to the chute 6 of the emergency shutdown reactor plate, so that the impact on the axial side surface of the emergency shutdown reactor plate 5 when the coolant flows axially is reduced; when the emergency stop stack plate 5 is not inserted into the fuel area, the stop stack plate chute 6 can be used for axial flow of coolant; the emergency shutdown plate 5 and the shutdown plate chute 6 extend axially through the entire core.
The radial reflecting layer 7 and the axial reflecting layer 8 are made of beryllium oxide materials; the axial reflecting layers 8 are tightly connected and arranged at two axial ends of the fuel area, a coolant flow channel 9 in the reflecting layers is arranged in the fuel area and used for allowing a coolant to pass through the reflecting layers along the axial direction, and the coolant flow channels 9 in the reflecting layers correspond to the flow channels of the beryllium oxide base fuel assembly 1 and the yttrium hydride base fuel assembly 2 one by one.
The geometric shape of the whole reactor core is a regular hexagonal prism, the height is 1.7m, and the opposite side distance is 1.373 m.
Compared with the prior art, the invention has the following advantages:
1. the emergency shutdown plate and the shutdown plate sliding groove in the emergency shutdown safety device are directly arranged at the position where the outermost layer of the reactor core fuel area is connected with the radial reflecting layer, and the embedded integrated design not only ensures that the reactor core has two sets of shutdown systems which independently operate and comprise the control rotary drum, but also reduces the space occupied by the introduction of the emergency shutdown safety device. In addition, the shutdown plate chute can also be used for axial flow of coolant, so that the heat exchange area of the reactor core can be effectively increased, and the heat exchange capacity is improved, thereby effectively slowing down the temperature resistance problem of the material.
2. The reactor core fuel area assembly uses fuel assemblies with the same fuel enrichment degree but with the moderator matrixes of beryllium oxide and yttrium hydride respectively, and is arranged in a fuel area ring in a partitioning manner according to the difference between the temperature resistance and the moderating performance of the moderator matrix materials, so that the reactor core power distribution is flattened, the reactor core power peak factor is reduced, and the nuclear fuel manufacturing difficulty caused by different fuel enrichment degrees is reduced. In addition, the excellent moderating performance and the characteristic of negative reactivity caused by high-temperature hydrogen loss of the yttrium hydride material not only reduce the requirement of fuel enrichment and the volume of the reactor core, but also enhance the inherent safety of the reactor core.
3. The spherical TRISO granular fuel with uranium carbide as a fuel core is used in the central columnar fuel area and the edge columnar fuel area in the beryllium oxide matrix fuel assembly and the yttrium hydride matrix fuel assembly, the fuel belongs to accident fault-tolerant fuel, and the safety of a reactor core can be ensured by the fuel, wherein the high uranium density of the uranium carbide not only ensures the life requirement of the reactor core, but also reduces the volume of the reactor core and enhances the maneuverability of the reactor core.
4. The design of the columnar fuel areas and the flow channels with different sizes is adopted at different positions of the fuel assembly, so that the heat exchange area can be greatly increased on the premise of meeting the requirement of the core life, and the heat exchange capacity of the core is improved. In addition, the fuel assembly is provided with a multi-layer material structure such as a graphite matrix, an assembly cladding, a moderator matrix and the like from the TRISO granular fuel to the coolant flow channel, so that the migration of radioactive substances to the coolant can be effectively slowed down, and the leakage risk of the radioactive substances is reduced.
Drawings
FIG. 1 is a radial schematic view of an integrated mobile air-cooled micro power reactor core.
Fig. 2 is a schematic cross-sectional view taken along a-a of fig. 1.
FIG. 3 is a schematic view of a core fuel assembly.
FIG. 4 is a schematic structural view of a spherical TRISO particulate fuel dispersed in a graphite matrix.
Fig. 5 is a schematic diagram of the structure of the scram safety device.
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, the reactor core of the integrated mobile gas-cooled micro power reactor is composed of a fuel area, a control rotary drum, an emergency shutdown safety device and a radial reflecting layer 7 from inside to outside in sequence in the radial direction, the geometric shape of the whole reactor core is a regular hexagonal prism, and the opposite edge distance is 1.373 m. The center of the reactor core is a fuel area, and the fuel area is formed by tightly arranging two components, namely a beryllium oxide matrix fuel component 1 and a yttrium hydride matrix fuel component 2, in a regular hexagonal grid array, wherein the number of the beryllium oxide matrix fuel components 1 is 37, and the number of the yttrium hydride matrix fuel components 2 is 72. In order to flatten the power distribution of the reactor core and reduce the power peak factor of the reactor core, the beryllium oxide matrix fuel assembly 1 and the yttrium hydride matrix fuel assembly 2 in the fuel area are arranged for 7 circles from inside to outside in the radial direction, the first 3 circles and the 5 th circle are the beryllium oxide matrix fuel assembly 1, and the 4 th, the 6 th and the 7 th circles are the yttrium hydride matrix fuel assembly 2.
As shown in fig. 1, in order to ensure reactivity control during normal operation of a reactor and safety of a reactor core in an emergency, the reactor core is provided with two shutdown systems, namely a control drum and an emergency shutdown safety device, which independently operate according to different working principles. Under normal operation conditions, reactivity control and normal shutdown of the reactor core are completed by the control drum, and under accident conditions, emergency shutdown of the reactor is completed by the emergency shutdown safety device. For the control rotary drum, the control rotary drum is composed of an arc absorber 3 and a control rotary drum base body 4, and the arc absorber 3 is tightly attached to the control rotary drum base body 4. In order to meet the normal control requirement and safety analysis rule of the reactor, the whole control drum is arranged in the radial reflecting layer 7 and is close to the outermost layer of the fuel zone, wherein the control drum base body 4 is made of beryllium oxide material and has an outer diameter of 9cm, and the arc-shaped absorber 3 is made of boron carbide with the boron-10 enrichment degree of 92% and has a thickness of 2 cm. For the emergency shutdown device, in order to reduce the occupied space of the emergency shutdown safety device as much as possible, the emergency shutdown safety device adopts an embedded integrated design, is arranged at the joint of a fuel area and a radial reflecting layer 7 and consists of an emergency shutdown plate 5 and a shutdown plate chute 6, and the emergency shutdown plate 5 is arranged in the shutdown plate chute 6. When the reactor core has a safety accident, the fuel zone can be radially inserted into the chute 6 of the shutdown plate to make the reactor be in emergency shutdown.
As shown in fig. 1 and 2, the radial reflecting layer 7 is closely attached to the radially outermost layer of the fuel region of the core, the axial reflecting layers 8 are closely attached to the axial ends of the fuel region, and the scram safety device of the core axially penetrates through the radial reflecting layer 7 and the axial reflecting layers 8. In order to reduce neutron leakage and improve the neutron economy of the reactor core, the radial reflecting layer 7 and the axial reflecting layer 8 are both preferably made of beryllium oxide materials, the thickness of the radial reflecting layer 7 is 34cm, and the thickness of the axial reflecting layer 8 is 25 cm. Wherein, the inner part of the axial reflecting layer 8 is provided with a coolant flow channel 9 in the reflecting layer for the coolant to pass through along the axial direction, and the coolant flow channel 9 in the reflecting layer is in one-to-one correspondence with the flow channels of the beryllium oxide base fuel assembly 1 and the yttrium hydride base fuel assembly 2. The axial height of the whole core is 1.7 m.
As shown in fig. 1 and 3, in order to ensure the compactness of the core structure, the beryllium oxide matrix fuel assembly 1 and the yttrium hydride matrix fuel assembly 2 are both in regular hexagon design, and have a pair distance of 6cm and a height of 1.2 m. In order to simultaneously meet the core life requirement and the core heat exchange requirement, the two assemblies adopt columnar fuel areas and flow channel designs with different sizes at different positions, each of the beryllium oxide substrate fuel assembly 1 and the yttrium hydride substrate fuel assembly 2 comprises an assembly cladding 15 and a moderator substrate 16 distributed in the assembly cladding 15, 1 central columnar fuel area 10, 6 assembly inner flow channels 11 and 6 edge columnar fuel areas 12 are sequentially arranged in the assembly cladding 15 from inside to outside, 6 edge central flow channels 13 and 6 corner flow channels 14 are arranged at intervals on the outer periphery of the assembly cladding 15, the radius of the central columnar fuel area 10 of each assembly is 0.9cm, the radius of the assembly inner flow channel 11 is 0.45cm, the radius of the edge columnar fuel area 12 is 0.7cm, the radius of the edge central flow channel 13 is 0.6cm, the radius of the corner flow channel 14 is 0.35cm, and the thickness of the assembly cladding 15 is 0.5 mm. In the beryllium oxide matrix fuel assembly 1, the moderator matrix 16 is a beryllium oxide material, while in the yttrium hydride matrix fuel assembly 2, the moderator matrix 16 is a yttrium hydride material. As for the component cladding 15, the material is preferably Mo-14Re alloy with better radiation resistance and mechanical property.
As shown in fig. 3 and 4, the central columnar fuel region 10 and the edge columnar fuel region 12 of the beryllium oxide matrix fuel assembly 1 and the yttrium hydride matrix fuel assembly 2 both adopt spherical TRISO particulate fuel which is randomly and uniformly dispersed in a graphite matrix 23 and has an enrichment degree of 19.75%, which belongs to accident fault-tolerant fuel, the safety of a reactor core can be ensured from the fuel, and a multi-barrier can be formed by utilizing the multilayer structure of the spherical TRISO particulate fuel, the assembly cladding 15 of the assembly and the moderator matrix 16, so that the migration of radioactive substances into a coolant is effectively slowed down, and the leakage risk of the radioactive substances is reduced. In order to meet the requirement of the reactor core on the life and reduce the volume of the reactor core as much as possible, the fuel kernel of the spherical TRISO granular fuel is made of uranium carbide material with high uranium density. The whole spherical TRISO granular fuel is sequentially a uranium carbide fuel particle inner core 18, a loose pyrolytic carbon layer 19, an inner compact pyrolytic carbon layer 20, a silicon carbide layer 21 and an outer compact pyrolytic carbon layer 22 from inside to outside, wherein the radius of the uranium carbide fuel particle inner core 18 is 0.275mm, the thickness of the loose pyrolytic carbon layer 19 is 0.07mm, the thickness of the inner compact pyrolytic carbon layer 20 is 0.04mm, the thickness of the silicon carbide layer 21 is 0.035mm, and the thickness of the outer compact pyrolytic carbon layer 22 is 0.04 mm.
As shown in figures 1 and 5, in order to meet the requirement of the reactor scram in the accident situation, the scram plate 5 is preferably made of boron carbide with the boron-10 enrichment degree of 92%, the whole shape is a cuboid, the thickness is 3.46cm, the height is 1.7m, the length is 26cm, and semicircular drag reduction flow channels 17 with the radius of 0.7cm are arranged on the surfaces of two sides of the scram plate chute 6 and are equidistantly arranged at the distance of 3.33cm for allowing the coolant to pass through so as to reduce the impact on the axial side face of the scram plate 5 when the coolant flows axially. In addition, under normal operating mode, when emergency shutdown heap 5 did not insert the fuel zone promptly, shutdown heap board spout 6 can supply the coolant axial flow to use in order to increase the reactor core heat transfer area, promotes heat transfer capacity to effectively slow down the temperature toleration problem of material.
Claims (9)
1. An integrated mobile air-cooled miniature power reactor core, which is characterized in that: the reactor core consists of a fuel area, a control rotary drum, an emergency shutdown safety device, a radial reflecting layer (7) and an axial reflecting layer (8) from inside to outside in sequence; the fuel area is arranged in the center of the reactor core and is formed by tightly arranging two components, namely a beryllium oxide matrix fuel component (1) and a yttrium hydride matrix fuel component (2), in a regular hexagonal grid array, the beryllium oxide matrix fuel component (1) is arranged on the inner ring of the fuel area, and the yttrium hydride matrix fuel component (2) is arranged on the outer ring of the fuel area; the control rotary drum is composed of an arc absorber (3) and a control rotary drum base body (4), the arc absorber (3) is tightly attached to the control rotary drum base body (4), and the whole control rotary drum is arranged in the radial reflecting layer (7) and is close to the outermost layer of the fuel zone; the emergency shutdown safety device consists of an emergency shutdown plate (5) and a shutdown plate sliding chute (6), wherein the shutdown plate sliding chute (6) is arranged at the joint of the fuel area and the radial reflecting layer (7) and axially penetrates through the radial reflecting layer (7) and the axial reflecting layer (8), the emergency shutdown plate (5) is arranged in the shutdown plate sliding chute (6) and can be radially inserted into the fuel area along the shutdown plate sliding chute (6) to emergently shutdown the reactor when the reactor core has a safety accident; the radial reflecting layer (7) is close to the radial outermost layer of the fuel area, and the axial reflecting layer (8) is tightly connected to the two axial ends of the fuel area.
2. The integrated mobile gas-cooled micropower reactor core of claim 1, wherein: the beryllium oxide substrate fuel assembly (1) and the yttrium hydride substrate fuel assembly (2) are both in regular hexagons and comprise assembly cladding (15) and moderator substrates (16) distributed in the assembly cladding (15), 1 central columnar fuel area (10), 6 assembly inner flow channels (11) and 6 edge columnar fuel areas (12) are sequentially arranged in the assembly cladding (15) from inside to outside, and 6 edge central flow channels (13) and 6 edge corner flow channels (14) are arranged at intervals on the outer periphery of the assembly cladding (15); the moderator base body (16) of the beryllium oxide base fuel assembly (1) adopts a beryllium oxide material, and the moderator base body (16) of the yttrium hydride base fuel assembly (2) adopts a yttrium hydride material; the component cladding (15) material is Mo-14Re alloy.
3. The integrated mobile gas-cooled micropower reactor core of claim 2, wherein: the central columnar fuel area (10) and the edge columnar fuel area (12) are composed of spherical TRISO granular fuel which is randomly and uniformly dispersed in a graphite matrix (23) and has the enrichment degree of 19.75%; the spherical TRISO granular fuel sequentially comprises a uranium carbide fuel particle inner core (18), a loose pyrolytic carbon layer (19), an inner compact pyrolytic carbon layer (20), a silicon carbide layer (21) and an outer compact pyrolytic carbon layer (22) from inside to outside, wherein the radius of the uranium carbide fuel particle inner core (18) is 0.275mm, the thickness of the loose pyrolytic carbon layer (19) is 0.07mm, the thickness of the inner compact pyrolytic carbon layer (20) is 0.04mm, the thickness of the silicon carbide layer (21) is 0.035mm, and the thickness of the outer compact pyrolytic carbon layer (22) is 0.04 mm.
4. The integrated mobile gas-cooled micropower reactor core of claim 2, wherein: the radius of the central columnar fuel area (10) is 0.9cm, the radius of the flow channel (11) in the assembly is 0.45cm, the radius of the edge columnar fuel area (12) is 0.7cm, the radius of the edge central flow channel (13) is 0.6cm, the radius of the corner flow channel (14) is 0.35cm, and the thickness of the assembly cladding (15) is 0.5 mm; the pair side distance of the beryllium oxide substrate fuel assembly (1) and the yttrium hydride substrate fuel assembly (2) is 6cm, and the height of the beryllium oxide substrate fuel assembly and the yttrium hydride substrate fuel assembly is 1.2 m.
5. The integrated mobile gas-cooled micropower reactor core of claim 2, wherein: the number of beryllium oxide substrate fuel assemblies (1) in the fuel area is 37, and the number of yttrium hydride substrate fuel assemblies (2) in the fuel area is 72; and the beryllium oxide matrix fuel assembly (1) and the yttrium hydride matrix fuel assembly (2) in the fuel area are arranged for 7 circles in total from inside to outside in the radial direction, the beryllium oxide matrix fuel assembly (1) is arranged in the first 3 circles and the beryllium oxide matrix fuel assembly (5) in the second 3 circles, and the yttrium hydride matrix fuel assembly (2) is arranged in the 4 th, the 6 th and the 7 th circles.
6. The integrated mobile gas-cooled micropower reactor core of claim 1, wherein: the control rotary drum base body (4) is made of beryllium oxide and has an outer diameter of 9cm, and the arc absorber (3) is made of boron carbide with a boron-10 enrichment degree of 92% and has a thickness of 2 cm.
7. The integrated mobile gas-cooled micropower reactor core of claim 1, wherein: the emergency shutdown stacking plate (5) is made of boron carbide with the boron-10 enrichment degree of 92%, the whole shape is a cuboid, and semicircular drag reduction flow channels (17) which are arranged at equal intervals are arranged on the surfaces of two sides of the emergency shutdown stacking plate chute (6) and are used for allowing a coolant to pass through so as to reduce the impact on the axial side face of the emergency shutdown stacking plate (5) when the coolant flows axially; when the emergency stop stack plate (5) is not inserted into the fuel area, the stack stop plate chute (6) can be used for axial flow of a coolant; the emergency reactor stopping plate (5) and the reactor stopping plate sliding groove (6) penetrate through the whole reactor core in the axial direction.
8. The integrated mobile gas-cooled micropower reactor core of claim 1, wherein: the radial reflecting layer (7) and the axial reflecting layer (8) are made of beryllium oxide; the axial reflecting layers (8) are tightly connected and arranged at two axial ends of the fuel area, a coolant flow channel (9) in the reflecting layers is arranged inside the fuel area and used for allowing coolant to pass through along the axial direction, and the coolant flow channel (9) in the reflecting layers corresponds to flow channels of the beryllium oxide base fuel assembly (1) and the yttrium hydride base fuel assembly (2) one by one.
9. The integrated mobile gas-cooled micropower reactor core of claim 1, wherein: the geometric shape of the whole reactor core is a regular hexagonal prism, the height is 1.7m, and the opposite side distance is 1.373 m.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210937620.2A CN115101221B (en) | 2022-08-05 | 2022-08-05 | Integrated movable air-cooled miniature power reactor core |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210937620.2A CN115101221B (en) | 2022-08-05 | 2022-08-05 | Integrated movable air-cooled miniature power reactor core |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN115101221A true CN115101221A (en) | 2022-09-23 |
| CN115101221B CN115101221B (en) | 2023-05-02 |
Family
ID=83300238
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202210937620.2A Active CN115101221B (en) | 2022-08-05 | 2022-08-05 | Integrated movable air-cooled miniature power reactor core |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN115101221B (en) |
Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3149043A (en) * | 1962-12-26 | 1964-09-15 | Goldstein Lester | Nuclear reactor |
| FR1472116A (en) * | 1965-02-08 | 1967-03-10 | Atomic Energy Authority Uk | Liquid retarder nuclear reactors |
| DE1589802B1 (en) * | 1963-02-18 | 1971-04-22 | Gulf Atomic Inc | Leistern nuclear reactor with negative temperature coefficient of reactivity |
| FR2953319A1 (en) * | 2009-12-02 | 2011-06-03 | Commissariat Energie Atomique | DEVICE AND METHOD FOR LOADING AND UNLOADING THE HEART OF A SODIUM CALOPORATOR NUCLEAR REACTOR AND SODIUM CALOPORER NUCLEAR REACTOR COMPRISING SUCH A DEVICE |
| CN110232979A (en) * | 2019-06-13 | 2019-09-13 | 西安交通大学 | A kind of open grid type air cooling nuclear reactor for space reactor core |
| CN110827998A (en) * | 2019-11-21 | 2020-02-21 | 中国核动力研究设计院 | Beryllium oxide moderated metal cooling reactor miniaturization design method and reactor |
| CN110853777A (en) * | 2019-11-07 | 2020-02-28 | 西安交通大学 | Fuel assembly structure for enhancing negative feedback of temperature of gas-cooled fast reactor and reactor core structure |
| CN112410600A (en) * | 2020-10-30 | 2021-02-26 | 北京科技大学 | Flash sintering preparation method of uranium-zirconium hydride and uranium-yttrium hydride fuel pellets |
| CN113270205A (en) * | 2021-03-29 | 2021-08-17 | 中国核电工程有限公司 | Modularized pressure pipe type gas-cooled micro-reactor core |
| CN114068043A (en) * | 2021-10-09 | 2022-02-18 | 中广核研究院有限公司 | Particulate dense fuel element |
-
2022
- 2022-08-05 CN CN202210937620.2A patent/CN115101221B/en active Active
Patent Citations (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3149043A (en) * | 1962-12-26 | 1964-09-15 | Goldstein Lester | Nuclear reactor |
| DE1589802B1 (en) * | 1963-02-18 | 1971-04-22 | Gulf Atomic Inc | Leistern nuclear reactor with negative temperature coefficient of reactivity |
| FR1472116A (en) * | 1965-02-08 | 1967-03-10 | Atomic Energy Authority Uk | Liquid retarder nuclear reactors |
| FR2953319A1 (en) * | 2009-12-02 | 2011-06-03 | Commissariat Energie Atomique | DEVICE AND METHOD FOR LOADING AND UNLOADING THE HEART OF A SODIUM CALOPORATOR NUCLEAR REACTOR AND SODIUM CALOPORER NUCLEAR REACTOR COMPRISING SUCH A DEVICE |
| CN110232979A (en) * | 2019-06-13 | 2019-09-13 | 西安交通大学 | A kind of open grid type air cooling nuclear reactor for space reactor core |
| CN110853777A (en) * | 2019-11-07 | 2020-02-28 | 西安交通大学 | Fuel assembly structure for enhancing negative feedback of temperature of gas-cooled fast reactor and reactor core structure |
| CN110827998A (en) * | 2019-11-21 | 2020-02-21 | 中国核动力研究设计院 | Beryllium oxide moderated metal cooling reactor miniaturization design method and reactor |
| CN112410600A (en) * | 2020-10-30 | 2021-02-26 | 北京科技大学 | Flash sintering preparation method of uranium-zirconium hydride and uranium-yttrium hydride fuel pellets |
| CN113270205A (en) * | 2021-03-29 | 2021-08-17 | 中国核电工程有限公司 | Modularized pressure pipe type gas-cooled micro-reactor core |
| CN114068043A (en) * | 2021-10-09 | 2022-02-18 | 中广核研究院有限公司 | Particulate dense fuel element |
Non-Patent Citations (4)
| Title |
|---|
| 刘利民;张大林;郑美银;秋穗正;苏光辉;田文喜;: "固态钍基熔盐堆堆芯物理参数计算" * |
| 杨谢;佘顶;石磊;: "棱柱式高温气冷空间核反应堆初步方案设计与中子物理分析", 原子能科学技术 * |
| 王立鹏;江新标;赵柱民;张信一;陈立新;: "热管式锂冷空间快堆中子学计算分析" * |
| 秦雪;李满仓;廖鸿宽;于颖锐;秦冬;蒋朱敏;王帅;蔡云;郭锐;: "基于FCM燃料的商业压水堆中子学分析", 核技术 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN115101221B (en) | 2023-05-02 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US20230112687A1 (en) | Integrated in-vessel neutron shield | |
| CN113270210B (en) | Reactor core structure of lightweight heat pipe reactor with low uranium loading capacity | |
| WO2022206064A1 (en) | Reactor core system and gas-cooled micro reactor | |
| CN111627572B (en) | Modularized molten salt reactor core and molten salt reactor | |
| CN110867262B (en) | Liquid metal cooling reactor based on improvement of fuel utilization rate and management method | |
| CN110853774B (en) | Zirconium hydride moderated metal cooling reactor miniaturization design method and reactor | |
| CN110491533B (en) | Double-layer cooling reactor core power generation system | |
| CN113270206B (en) | Small prismatic annular gas-cooled micro-reactor core system with densely arranged coolant channels | |
| WO2022206072A1 (en) | Gas-cooled micro-reactor core and gas-cooled micro-reactor | |
| CN114121308A (en) | Reactor core structure of lead bismuth cooling fast neutron research reactor with ultra-high flux | |
| CN112331369B (en) | Ocean silent type heat pipe reactor power system | |
| CN116110619A (en) | Air-cooled micro-reactor fuel assembly and air-cooled micro-reactor core system | |
| CN115101221B (en) | Integrated movable air-cooled miniature power reactor core | |
| CN114496314B (en) | Ultra-high flux reactor core with fast neutron thermal neutron concentric circle type partition | |
| CN115938613A (en) | Transportable gas-cooled micro-reactor core system | |
| CN113205892B (en) | Reactor core system of prismatic gas-cooled micro-reactor | |
| Ohashi et al. | Modular high temperature reactor (Modular HTR) contributing the global environment protection | |
| CN115171924A (en) | Lead bismuth cooling solid reactor core system | |
| KR20190098611A (en) | Fuel block, nuclear reactor core having the fuel block, micro high temperature gas-cooled reactor having the nuclear reactor core | |
| CN112366010A (en) | First circulation loading method for applying FCM fuel to million kilowatt pressurized water reactor | |
| CN112216408A (en) | Fuel element, high-temperature gas-cooled reactor and high-temperature gas-cooled reactor system | |
| CN114496313B (en) | Ultra-high flux reactor core with fan-shaped partitions of fast neutrons and thermal neutrons | |
| CN217214160U (en) | Graphite-based dispersed fuel heat pipe reactor core structure with partitioned arrangement | |
| CN116612908A (en) | Lead bismuth cooling reactor core structure with inherent safety | |
| CN213815564U (en) | Fuel element, high-temperature gas-cooled reactor and high-temperature gas-cooled reactor system |
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 |