CN113130097A - High-efficiency heat-conducting heat pipe reactor fuel element - Google Patents
High-efficiency heat-conducting heat pipe reactor fuel element Download PDFInfo
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- CN113130097A CN113130097A CN202110277291.9A CN202110277291A CN113130097A CN 113130097 A CN113130097 A CN 113130097A CN 202110277291 A CN202110277291 A CN 202110277291A CN 113130097 A CN113130097 A CN 113130097A
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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
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/08—Casings; Jackets provided with external means to promote heat-transfer, e.g. fins, baffles
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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
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
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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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Abstract
The invention relates to a heat pipe reactor fuel element with high-efficiency heat conduction, which comprises nuclear fuel, a cladding pipe, a heat pipe and a heat conduction ring, wherein the cladding pipe comprises an inner wall and an outer wall which are sleeved, the heat pipe is arranged in an inner hole of the inner wall, and the heat conduction ring is sleeved outside the heat pipe and is positioned between the heat pipe and the inner wall; a plurality of axial heat-conducting plates and a plurality of radial heat-conducting plates are arranged between the inner wall and the outer wall of the cladding tube, the cladding tube is divided into a plurality of fuel areas for filling the nuclear fuel by the axial guide plates and the radial guide plates, and the axial guide plates are provided with stress release grooves. The high-efficiency heat-conducting heat pipe reactor fuel element is characterized in that nuclear fuel is arranged in a cladding pipe, and nuclear heat generated by operation is transferred to a heat pipe through the wall of the cladding pipe; the axial and radial heat conducting plates are arranged in the cladding tube and are used for assisting in efficient heat conduction; the heat pipe is arranged at the central position of the fuel element and conducts the heat of the core out of the reactor; the heat conducting ring is arranged between the heat pipe and the cladding pipe, so that the heat pipe and the cladding pipe are in contact heat transfer.
Description
Technical Field
The invention relates to the relevant technical field of reactors, in particular to a heat pipe reactor fuel element with high-efficiency heat conduction.
Background
The heat pipe reactor is a reactor with better space nuclear power application prospect at present, the nuclear fuel matched with the heat pipe passive heat conduction is a hot spot for researching foreign space nuclear power, and the existing nuclear fuel uses UO2The reactor mainly has low thermal conductivity, which is a bottleneck for restricting the increase of power density and the reduction of volume and weight of the reactor, and in order to improve the heat conductivity, the existing scheme adopts heat pipes and fuel rods to be arranged at intervals, and the heat conductivity is improved by arranging the heat pipes, so that the nuclear fuel share is relatively reduced, and the reactor is not beneficial to the small-sized and light-weighted design.
Disclosure of Invention
The invention aims to solve the technical problem of providing a heat pipe reactor fuel element with high-efficiency heat conduction aiming at the defects of the prior art.
The technical scheme for solving the technical problems is as follows: a high-efficiency heat-conducting heat pipe reactor fuel element comprises nuclear fuel, a cladding pipe, a heat pipe and a heat conducting ring, wherein the cladding pipe comprises an inner wall and an outer wall which are sleeved, the heat pipe is arranged in an inner hole of the inner wall, and the heat conducting ring is sleeved outside the heat pipe and is positioned between the heat pipe and the inner wall; the nuclear fuel cladding tube is characterized in that a plurality of axial heat-conducting plates and a plurality of radial heat-conducting plates are arranged between the inner wall and the outer wall of the cladding tube, the cladding tube is divided into a plurality of fuel areas for filling nuclear fuel by the axial guide plates and the radial guide plates, and the axial guide plates are provided with stress release grooves.
The invention has the beneficial effects that: the high-efficiency heat-conducting heat pipe reactor fuel element is characterized in that nuclear fuel is arranged in a cladding pipe, and nuclear heat generated by operation is transferred to a heat pipe through the wall of the cladding pipe; the axial and radial heat conducting plates are arranged in the cladding tube and are used for assisting in efficient heat conduction; the heat pipe is arranged at the central position of the fuel element and conducts the heat of the core out of the reactor; the heat conducting ring is arranged between the heat pipe and the cladding pipe, so that the heat pipe and the cladding pipe are in contact heat transfer. The invention improves the heat-conducting property of the fuel element through the heat-conducting structure so as to improve the power density of the reactor and realize the miniaturized compact design.
On the basis of the technical scheme, the invention can be further improved as follows.
Further, the stress relief groove is formed in the radial direction of the axial heat conduction plate and penetrates through the inner hole and the outer peripheral side of the axial heat conduction plate.
The beneficial effect of adopting the further scheme is that: safe and reliable, through design stress relief groove structure, solve the thermal stress concentration problem and can realize reducing structure thermal stress, improve structure security.
Further, the width of the groove gap of the stress release groove is 0.2-0.5mm, and the depth of the groove gap is at least half of the thickness of the axial heat conducting plate.
The beneficial effect of adopting the further scheme is that: the axial heat conducting plate radially penetrates through the fuel area and is directly connected with the central heat conducting ring and the heat pipe, the general temperature gradient of the nuclear fuel is large, large thermal stress can be brought, and the stress releasing groove can release the thermal stress and ensure the structural safety. The width of the groove gap of the stress relief groove is 0.2-0.5mm, the depth of the groove gap is at least half of the thickness of the axial heat conducting plate, and after the stress relief groove is designed through finite element analysis and demonstration, under the same working condition, the maximum structural thermal stress is reduced to about 100MPa from more than 200MPa, the structural stress is obviously reduced, and the structural safety is ensured. The structure is applied to the use of UO2Reactor design for fuel, at UO2Under the condition that the heat conductivity of the fuel is not enough than that of the foreign advanced metal fuel 1/10, the size of the reactor is close to that of the foreign design, meanwhile, the heat of the reactor core can be smoothly led out, and the structure safety is ensured.
Further, a plurality of radial direction deflectors are arranged along the axial interval of cladding pipe, the week side of radial direction deflector and periphery side respectively with the inner wall and the outer wall of cladding pipe are connected, adjacent two be equipped with a plurality of between the radial direction deflector axial direction deflector, a plurality of axial direction deflector is along the radial of cladding pipe is radial arrangement.
The beneficial effect of adopting the further scheme is that: through the axial heat-conducting plate and the radial heat-conducting plate with high heat conductivity, the hot fuel is divided into an axial region and a radial region, the thickness of the heat-conducting structure is designed according to heat power distribution, and a heat-conducting path is optimized, so that high-efficiency heat conduction is realized.
Further, the radial heat-conducting plates are arranged in the direction perpendicular to the axial direction of the cladding tube, and the axial guide plates are arranged perpendicular to the radial heat-conducting plates.
Furthermore, a plurality of open slots are respectively formed at two ends of the heat conduction ring, and the open slots at the two ends of the heat conduction ring are arranged in a staggered mode.
The beneficial effect of adopting the further scheme is that: the open slot is formed in the heat conduction ring, so that the strength can be reduced, the thermal expansion amount of the structure can be contained, and the extrusion damage of thermal expansion to the cladding tube and the heat pipe is reduced.
Furthermore, the width of the gap of the open groove is 0.1-0.3mm, and the opening depth of the open groove is 1/2-2/3 of the total length of the heat conduction ring.
Further, the thickness of the axial heat conducting plate is gradually reduced along the direction from the middle part to the two ends of the cladding tube.
The beneficial effect of adopting the further scheme is that: according to the power density distribution of different positions of the fuel element, generally, the thermal power of the central area of the fuel is high, so that the thickness of the middle shaft to the heat conducting plate is large, and the heat conducting efficiency is improved; the thermal power density of the two ends and the edge area of the fuel is low, so the thickness of the edge axial heat-conducting plate is gradually reduced to adapt to the heat-conducting requirements of different areas, the layer at the middle of the axial heat-conducting plate is thickest according to the requirements, the thickness can be selected to be 6mm, the thicknesses of the two side plates are gradually reduced, and respectively, the thicknesses can be selected to be 5mm and 4 mm.
Further, the axial heat-conducting plate and the radial heat-conducting plate are respectively fixedly connected with the cladding tube.
The beneficial effect of adopting the further scheme is that: the axial heat conducting plate is connected with the cladding tube in a segmented mode, and generally, the connection modes such as welding and the like can be adopted. The two wings of the radial heat conducting plate can be respectively connected with the inner wall and the outer wall of the cladding tube in a welding mode and the like.
Furthermore, the number of the radial heat conduction plates is 6, and the included angle between every two adjacent radial heat conduction plates is 60 degrees; the axial heat-conducting plate is 5 pieces.
The beneficial effect of adopting the further scheme is that: the cladding tube is internally provided with a plurality of axial heat-conducting plates and radial heat-conducting plates, the axial heat-conducting plates can adopt 5 blocks, the cladding tube is divided into 4 sections, further, the fuel is axially partitioned, two wings of the radial heat-conducting plates are respectively connected with the inner wall and the outer wall of the cladding tube and are generally uniformly distributed, for example, the fuel is radially divided into 6 blocks by adopting 60-degree uniform distribution, so that the heat emitted by the fuel is transmitted to the heat tube along a better path, and the high-efficiency heat conduction is realized.
Drawings
FIG. 1 is a schematic cross-sectional view of a heat pipe reactor fuel cell of the present invention with high heat conductivity;
FIG. 2 is a schematic side view of a high efficiency heat conducting heat pipe reactor fuel cell according to the present invention;
fig. 3 is a schematic view of the radial heat-conducting plate according to the present invention.
In the drawings, the components represented by the respective reference numerals are listed below:
400. a cladding tube; 401. a nuclear fuel; 402. a heat pipe; 403. a heat conducting ring; 404. an outer wall; 405. an inner wall; 406. a radial heat conducting plate; 407. an axial heat conducting plate; 408. a stress relief groove.
Detailed Description
The principles and features of this invention are described below in conjunction with the following drawings, which are set forth by way of illustration only and are not intended to limit the scope of the invention.
Example 1
As shown in fig. 1-3, the high-efficiency heat-conducting heat pipe reactor fuel element of the embodiment includes a nuclear fuel 401, a cladding pipe 400, a heat pipe 402 and a heat-conducting ring 403, where the cladding pipe 400 includes an inner wall 405 and an outer wall 404 that are sleeved, the heat pipe 402 is disposed in an inner hole of the inner wall 405, and the heat-conducting ring 403 is sleeved outside the heat pipe 402 and is located between the heat pipe 402 and the inner wall 405; a plurality of axial heat-conducting plates 407 and a plurality of radial heat-conducting plates 406 are disposed between the inner wall 405 and the outer wall 404 of the cladding 400, the axial guide plates 407 and the radial guide plates 406 divide the cladding 400 into a plurality of fuel zones for filling the nuclear fuel 401, and the axial guide plates 407 are provided with stress relief grooves 408.
According to the high-efficiency heat-conducting heat pipe reactor fuel element, nuclear fuel is placed in the cladding pipe, and nuclear heat generated in operation is transferred to the heat pipe through the wall of the cladding pipe; the axial and radial heat conducting plates are arranged in the cladding tube and are used for assisting in efficient heat conduction; the heat pipe is arranged at the central position of the fuel element and conducts the heat of the core out of the reactor; the heat conducting ring is arranged between the heat pipe and the cladding pipe, so that the heat pipe and the cladding pipe are in contact heat transfer. The axial heat conducting plate of the embodiment divides the fuel into a plurality of layers in the height direction, the radial heat conducting plate evenly divides the fuel into a plurality of areas in the radial direction, and the axial heat conducting plate and the radial heat conducting plate are combined to optimize a heat conducting path so as to realize the high-efficiency export of the heat generated by the fuel. The heat conduction structure of this embodiment has improved fuel element's heat conductivility, because structural heat conduction efficiency is high, can further improve power density on the basis that traditional fuel rod and heat pipe were arranged alternately, be favorable to reducing reactor volume and weight to improve reactor power density, realize miniaturized compact design. The heat conduction ring is arranged between the inner wall of the cladding tube and the heat pipe, the outer wall of the heat conduction ring is matched with the inner wall of the cladding tube, the inner hole of the heat conduction ring is matched with the heat pipe, and the heat conduction gap between the cladding tube and the heat pipe is compensated through the thermal expansion of the heat conduction ring, so that the heat conduction between the cladding tube and the heat pipe is realized.
Example 2
As shown in fig. 1-3, the high-efficiency heat-conducting heat pipe reactor fuel element of the embodiment includes a nuclear fuel 401, a cladding pipe 400, a heat pipe 402 and a heat-conducting ring 403, where the cladding pipe 400 includes an inner wall 405 and an outer wall 404 that are sleeved, the heat pipe 402 is disposed in an inner hole of the inner wall 405, and the heat-conducting ring 403 is sleeved outside the heat pipe 402 and is located between the heat pipe 402 and the inner wall 405; a plurality of axial heat-conducting plates 407 and a plurality of radial heat-conducting plates 406 are disposed between the inner wall 405 and the outer wall 404 of the cladding 400, the axial guide plates 407 and the radial guide plates 406 divide the cladding 400 into a plurality of fuel zones for filling the nuclear fuel 401, and the axial guide plates 407 are provided with stress relief grooves 408.
As shown in fig. 3, the stress relief groove 408 of the present embodiment is opened in the radial direction of the axial heat-conducting plate 407 and penetrates through the inner hole and the outer circumferential side of the axial heat-conducting plate 407. Safe and reliable, through design stress relief groove structure, solve the thermal stress concentration problem and can realize reducing structure thermal stress, improve structure security, be applicable to high temperature environment and use.
As shown in fig. 3, the stress relief groove 408 of the present embodiment has a groove gap width of 0.2-0.5mm and a depth of at least half of the thickness of the axial heat-conducting plate 407. The axial heat conducting plate radially penetrates through the fuel area and is directly connected with the central heat conducting ring and the heat pipe, the general temperature gradient of the nuclear fuel is large, large thermal stress can be brought, and the stress releasing groove can release the thermal stress and ensure the structural safety. The width of the groove gap of the stress relief groove is 0.2-0.5mm, the depth of the groove gap is at least half of the thickness of the axial heat conducting plate, and after the stress relief groove is designed through finite element analysis and demonstration, under the same working condition, the maximum structural thermal stress is reduced to about 100MPa from more than 200MPa, the structural stress is obviously reduced, and the structural safety is ensured. The structure is applied to the use of UO2Reactor design for fuel, at UO2Under the condition that the heat conductivity of the fuel is not enough than that of the foreign advanced metal fuel 1/10, the size of the reactor is close to that of the foreign design, meanwhile, the heat of the reactor core can be smoothly led out, and the structure safety is ensured.
As shown in fig. 1 and 2, the plurality of radial guide plates 406 are arranged at intervals along the axial direction of the cladding tube 400, the inner circumferential side and the outer circumferential side of the radial guide plates 406 are respectively connected with the inner wall 405 and the outer wall 404 of the cladding tube 400, the plurality of axial guide plates 407 are arranged between two adjacent radial guide plates 406, and the plurality of axial guide plates 407 are radially arranged along the radial direction of the cladding tube 400. Through the axial heat-conducting plate and the radial heat-conducting plate with high heat conductivity, the hot fuel is divided into an axial region and a radial region, the thickness of the heat-conducting structure is designed according to heat power distribution, and a heat-conducting path is optimized, so that high-efficiency heat conduction is realized.
As shown in fig. 1, the radial heat-conducting plate 406 is arranged in a direction perpendicular to the axial direction of the cladding tube 400, and the axial guide plate 407 is arranged perpendicular to the radial heat-conducting plate 406.
In this embodiment, a plurality of open slots are respectively formed at two ends of the heat-conducting ring 403, and the open slots at two ends of the heat-conducting ring 403 are arranged in a staggered manner. The open slot is formed in the heat conduction ring, so that the strength can be reduced, the thermal expansion amount of the structure can be contained, and the extrusion damage of thermal expansion to the cladding tube and the heat pipe is reduced. The heat conduction ring 403 of the present embodiment has a material expansion coefficient higher than that of the structural material, compensates for the gaps after thermal expansion, realizes efficient contact heat transfer, has a material strength lower than that of the structural material, and has a symmetrically and uniformly distributed open slot structure to accommodate the design allowance of self expansion, thereby avoiding the structural material from being damaged by expansion. The material of the heat conduction ring can be selected from alloy materials, such as nickel alloy, stainless steel and the like. The heat conduction ring has lower strength and high thermal expansion coefficient under the operation condition so as to realize the contact heat transfer between the cladding tube and the heat pipe through the high thermal expansion of the heat conduction ring.
The width of the gap of the open groove is 0.1-0.3mm, and the opening depth of the open groove is 1/2-2/3 of the total length of the heat conduction ring.
As shown in fig. 1, the thickness of the axial heat-conducting plate 407 is gradually reduced in the direction from the middle to both ends of the cladding tube 400 in this embodiment. According to the power density distribution of different positions of the fuel element, generally, the thermal power of the central area of the fuel is high, so that the thickness of the middle shaft to the heat conducting plate is large, and the heat conducting efficiency is improved; the thermal power density of the two ends and the edge area of the fuel is low, so the thickness of the edge axial heat-conducting plate is gradually reduced to adapt to the heat-conducting requirements of different areas, the layer at the middle of the axial heat-conducting plate is thickest according to the requirements, the thickness can be selected to be 6mm, the thicknesses of the two side plates are gradually reduced, and respectively, the thicknesses can be selected to be 5mm and 4 mm.
As shown in fig. 1, the axial heat-conducting plate 407 and the radial heat-conducting plate 406 of the present embodiment are fixedly connected to the cladding tube 400, respectively. The axial heat conducting plate is connected with the cladding tube in a segmented mode, and generally, the connection modes such as welding or bonding can be adopted. The two wings of the radial heat conducting plate can be respectively connected with the inner wall and the outer wall of the cladding tube in a welding or bonding mode and the like. The radial heat-conducting plate and the cladding tube can be integrally processed and molded, the nuclear fuel is divided into a plurality of blocks, and the heat-conducting requirements of different power densities are matched by adjusting the thickness of the axial heat-conducting plate.
As shown in fig. 1, the radial heat-conducting plates 406 of this embodiment are 6, and the included angle between two adjacent radial heat-conducting plates 406 is 60 °; the axial heat-conducting plate 407 is 5 pieces. The cladding tube is internally provided with a plurality of axial heat-conducting plates and radial heat-conducting plates, the axial heat-conducting plates can adopt 5 blocks, the cladding tube is divided into 4 sections, further, the fuel is axially partitioned, two wings of the radial heat-conducting plates are respectively connected with the inner wall and the outer wall of the cladding tube and are generally uniformly distributed, for example, the fuel is radially divided into 6 blocks by adopting 60-degree uniform distribution, so that the heat emitted by the fuel is transmitted to the heat tube along a better path, and the high-efficiency heat conduction is realized.
According to the high-efficiency heat-conducting heat pipe reactor fuel element, nuclear fuel is placed in the cladding pipe, and nuclear heat generated in operation is transferred to the heat pipe through the wall of the cladding pipe; the axial and radial heat conducting plates are arranged in the cladding tube and are used for assisting in efficient heat conduction; the heat pipe is arranged at the central position of the fuel element and conducts the heat of the core out of the reactor; the heat conducting ring is arranged between the heat pipe and the cladding pipe, so that the heat pipe and the cladding pipe are in contact heat transfer. The axial heat conducting plate of the embodiment divides the fuel into a plurality of layers in the height direction, the radial heat conducting plate evenly divides the fuel into a plurality of areas in the radial direction, and the axial heat conducting plate and the radial heat conducting plate are combined to optimize a heat conducting path so as to realize the high-efficiency export of the heat generated by the fuel. The heat conduction structure of this embodiment has improved fuel element's heat conductivility, because structural heat conduction efficiency is high, can further improve power density on the basis that traditional fuel rod and heat pipe were arranged alternately, be favorable to reducing reactor volume and weight to improve reactor power density, realize miniaturized compact design. The heat conduction ring is arranged between the inner wall of the cladding tube and the heat pipe, the outer wall of the heat conduction ring is matched with the inner wall of the cladding tube, the inner hole of the heat conduction ring is matched with the heat pipe, and the heat conduction gap between the cladding tube and the heat pipe is compensated through the thermal expansion of the heat conduction ring, so that the heat conduction between the cladding tube and the heat pipe is realized.
In the description of the present invention, it is to be understood that the terms "central," "longitudinal," "lateral," "length," "width," "thickness," "upper," "lower," "front," "rear," "left," "right," "vertical," "horizontal," "top," "bottom," "inner," "outer," "clockwise," "counterclockwise," "axial," "radial," "circumferential," and the like are used in the orientations and positional relationships indicated in the drawings for convenience in describing the invention and to simplify the description, and are not intended to indicate or imply that the referenced devices or elements must have a particular orientation, be constructed and operated in a particular orientation, and are therefore not to be considered limiting of the invention.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one such feature. In the description of the present invention, "a plurality" means at least two, e.g., two, three, etc., unless specifically limited otherwise.
In the present invention, unless otherwise expressly stated or limited, the terms "mounted," "connected," "secured," and the like are to be construed broadly and can, for example, be fixedly connected, detachably connected, or integrally formed; can be mechanically or electrically connected; they may be directly connected or indirectly connected through intervening media, or they may be connected internally or in any other suitable relationship, unless expressly stated otherwise. The specific meanings of the above terms in the present invention can be understood by those skilled in the art according to specific situations.
In the present invention, unless otherwise expressly stated or limited, the first feature "on" or "under" the second feature may be directly contacting the first and second features or indirectly contacting the first and second features through an intermediate. Also, a first feature "on," "over," and "above" a second feature may be directly or diagonally above the second feature, or may simply indicate that the first feature is at a higher level than the second feature. A first feature being "under," "below," and "beneath" a second feature may be directly under or obliquely under the first feature, or may simply mean that the first feature is at a lesser elevation than the second feature.
In the description herein, references to the description of the term "one embodiment," "some embodiments," "an example," "a specific example," or "some examples," etc., mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the invention. In this specification, the schematic representations of the terms used above are not necessarily intended to refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, various embodiments or examples and features of different embodiments or examples described in this specification can be combined and combined by one skilled in the art without contradiction.
Although embodiments of the present invention have been shown and described above, it is understood that the above embodiments are exemplary and should not be construed as limiting the present invention, and that variations, modifications, substitutions and alterations can be made to the above embodiments by those of ordinary skill in the art within the scope of the present invention.
Claims (10)
1. A high-efficiency heat-conducting heat pipe reactor fuel element is characterized by comprising nuclear fuel, a cladding pipe, a heat pipe and a heat-conducting ring, wherein the cladding pipe comprises an inner wall and an outer wall which are sleeved, the heat pipe is arranged in an inner hole of the inner wall, and the heat-conducting ring is sleeved outside the heat pipe and is positioned between the heat pipe and the inner wall; the nuclear fuel cladding tube is characterized in that a plurality of axial heat-conducting plates and a plurality of radial heat-conducting plates are arranged between the inner wall and the outer wall of the cladding tube, the cladding tube is divided into a plurality of fuel areas for filling nuclear fuel by the axial guide plates and the radial guide plates, and the axial guide plates are provided with stress release grooves.
2. A high efficiency heat pipe reactor fuel element as claimed in claim 1, wherein said stress relief groove is formed along the radial direction of said axial heat conducting plate and penetrates the inner hole and the outer peripheral side of said axial heat conducting plate.
3. A high efficiency heat pipe reactor fuel element as claimed in claim 1 wherein the stress relief groove has a groove gap width of 0.2-0.5mm and a depth of at least half the thickness of the axial heat conducting plate.
4. A high efficiency heat pipe reactor fuel element according to claim 1, wherein a plurality of said radial guide plates are arranged at intervals along the axial direction of said cladding pipe, the inner circumferential side and the outer circumferential side of said radial guide plates are respectively connected to the inner wall and the outer wall of said cladding pipe, a plurality of said axial guide plates are arranged between two adjacent radial guide plates, and a plurality of said axial guide plates are arranged radially along the radial direction of said cladding pipe.
5. A high efficiency heat transfer tube reactor fuel element as claimed in claim 4 wherein said radially conductive plates are arranged in a direction perpendicular to the axial direction of said cladding tube and said axially oriented plates are arranged perpendicular to said radially conductive plates.
6. A high efficiency heat pipe reactor fuel element as claimed in any one of claims 1 to 5, wherein the heat conduction ring has a plurality of open slots at both ends, and the open slots at both ends of the heat conduction ring are staggered.
7. A high efficiency heat pipe reactor fuel element as claimed in claim 6 wherein the width of the open slot gap is 0.1-0.3mm and the open depth of the open slot is 1/2-2/3 of the total length of the heat conducting ring.
8. A high efficiency heat pipe reactor fuel element as claimed in any one of claims 1 to 5 wherein the thickness of the axial heat conducting plate decreases in a direction from the middle to the ends of the cladding tube.
9. A high efficiency heat pipe reactor fuel element as claimed in any one of claims 1 to 5 wherein the axially and radially conducting plates are each fixedly attached to the cladding tube.
10. A high efficiency heat pipe reactor fuel element as claimed in any one of claims 1 to 5 wherein the number of said heat conducting plates is 6, and the angle between two adjacent heat conducting plates is 60 °; the axial heat-conducting plate is 5 pieces.
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| CN115662659A (en) * | 2022-11-25 | 2023-01-31 | 中国科学院合肥物质科学研究院 | High specific power reactor core structure of heat pipe reactor |
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| US20180033501A1 (en) * | 2016-08-01 | 2018-02-01 | Kabushiki Kaisha Toshiba | Nuclear reactor and a method of heat transfer from a core |
| CN111066092A (en) * | 2018-08-16 | 2020-04-24 | 俄罗斯联邦国家科学中心-以A·I·利普斯基命名的物理和动力工程研究所股份公司 | Nuclear reactor core |
| CN111081391A (en) * | 2019-12-31 | 2020-04-28 | 中国核动力研究设计院 | Reactor core structure of heat pipe reactor fuel element adopting hexagonal prism cladding |
| CN111477354A (en) * | 2020-05-25 | 2020-07-31 | 中国原子能科学研究院 | Co-extrusion annular fuel rod |
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| CN113990527A (en) * | 2021-10-28 | 2022-01-28 | 中国核动力研究设计院 | Solid reactor core structure of heat pipe reactor |
| CN115662659A (en) * | 2022-11-25 | 2023-01-31 | 中国科学院合肥物质科学研究院 | High specific power reactor core structure of heat pipe reactor |
| CN115662659B (en) * | 2022-11-25 | 2023-05-05 | 中国科学院合肥物质科学研究院 | Heat pipe pile high specific power reactor core structure |
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