CN206516360U - A kind of nuclear fuel element - Google Patents

A kind of nuclear fuel element Download PDF

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Publication number
CN206516360U
CN206516360U CN201621467758.7U CN201621467758U CN206516360U CN 206516360 U CN206516360 U CN 206516360U CN 201621467758 U CN201621467758 U CN 201621467758U CN 206516360 U CN206516360 U CN 206516360U
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China
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nuclear fuel
fuel element
hypostracum
outer shell
section
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CN201621467758.7U
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Chinese (zh)
Inventor
周涛
马栋梁
齐实
陈柏旭
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North China Electric Power University
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North China Electric Power University
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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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  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The utility model discloses a kind of nuclear fuel element, the nuclear fuel element (100) includes outer shell (1) and hypostracum (2), forms enclosed construction between the outer shell (1) and hypostracum (2) to load fuel pellet (3)；Nuclear fuel element (100) is tubular structure, and its hypostracum (2) is internally formed outside hollow duct area (4), the hollow duct area (4) and outer shell (1) and passes to cooling agent.Nuclear fuel element has inside and outside hollow duct area, nuclear fuel element by cooling agent in the utility model, greatly improves the heat transfer efficiency of nuclear fuel element, can be prevented effectively from the possibility of the not enough initiation accident of nuclear fuel element cooling effect.

Description

A kind of nuclear fuel element
Technical field
The utility model is related to nuclear energy source domain, and more particularly to a kind of nuclear fuel with inside and outside Double-protection structure is first Part.
Background technology
Nuclear fuel element is supporting substances indispensable during modern society's nuclear energy is applied.For easily manufactured, Mou Xiehe Fuel element is often designed as solid shape structure, such as solid cylinder type Nuclear Fuel Element generally used now, the core of hexagonal pyramid form Spherical nuclear fuel element in fuel element, forth generation HTGR etc..Even if can the heat in nuclear reactor effectively Taken away by cooling agent, be a very important Consideration in nuclear power station design, especially in the feelings for occurring major accident Under condition, the generation effectively taken away residual heat of nuclear core, avoid reactor from melting the accidents such as heap is more needed.Nuclear fuel element internal high temperature The heat medium that can not effectively be cooled is taken away, and is the problem of faced one of nuclear fuel element is important.
Therefore, the present inventor is studied nuclear fuel element, a kind of anti-suitable for core with high heat transfer intensity to provide Answer the nuclear fuel element of heap.
Utility model content
In order to solve the above problems, present inventor has performed studying with keen determination, as a result find：Nuclear fuel element is carried out hollow By cooling agent inside and outside design, nuclear fuel element, the heat transfer efficiency of nuclear fuel element is greatly improved, core combustion can be prevented effectively from Expect that element cooling capacity deficiency, the molten heap accident risk of generation in the case of major accident are higher and after reactor shutdown Residual heat of nuclear core can not be exported into problem encountered quickly, so as to complete the utility model.
The purpose of this utility model is to provide a kind of nuclear fuel element, and the nuclear fuel element 100 includes the He of outer shell 1 Hypostracum 2, forms enclosed construction to load fuel pellet 3 between the outer shell 1 and hypostracum 2；
Nuclear fuel element 100 is tubular structure, and its hypostracum 2 is internally formed hollow duct area 4, the hollow duct area 4 Cooling agent is passed to outside outer shell 1.
A kind of nuclear fuel element provided according to the utility model, has the advantages that：
(1) nuclear fuel element has inside and outside hollow duct area, nuclear fuel element by cooling agent, pole in the utility model The big heat transfer efficiency for improving nuclear fuel element, can be prevented effectively from nuclear fuel element and molten heap accident occurs in the case of major accident Possibility；
(2) the utility model sets bulge-structure on the housing contacted with cooling agent, makes cooling agent formation turbulent flow, can be with The generation of laminar boundary layer effectively is prevented, and the cooling agent Secondary Flow thus formed can be fully by inside nuclear fuel element Hot-fluid take away, improve heat transfer efficiency；
(3) outer shell and hypostracum include separation layer and radiation protection layer in the utility model, reduce further core The risk of leakage；
(4) nuclear fuel element design principle is clear in the utility model, simple in construction, can effectively, economically by scale Manufacture with changing, as a kind of safe and reliable nuclear fuel element.
Brief description of the drawings
Fig. 1 shows the structural representation of nuclear fuel element in the utility model；
Fig. 2 shows the structural representation that nuclear fuel element main cross section in the utility model is triangular ring；
Fig. 3 shows the structural representation that nuclear fuel element main cross section in the utility model is annular；
Fig. 4 shows a kind of nuclear fuel element main cross section structural representation of preferred embodiment in the utility model；
Fig. 5 shows the sectional view of nuclear fuel element line A-A along along Fig. 4；
Fig. 6 shows raised structural representation on nuclear fuel element；
Fig. 7 shows in the utility model in a kind of preferred embodiment showing for raised Structural assignments mode on radiation protection layer It is intended to；
Fig. 8 shows in the utility model element interface and delivery port on the upper cover or low head of a kind of preferred embodiment Distribution schematic diagram；
Fig. 9 shows a kind of arrangement mode of nuclear fuel assembly center fuel element in preferred embodiment in the utility model Schematic diagram.
Drawing reference numeral explanation：
100- nuclear fuel elements；
1- outer shells；
11- separation layers I；
12- radiation protection layers I；
121- bulge-structures I；
2- and hypostracum；
21- separation layers II；
22- radiation protection layers II；
221- bulge-structures II；
3- fuel pellets；
4- hollow ducts area；
200- element interfaces；
300- delivery ports.
Embodiment
It is described in detail below by the utility model, the characteristics of the utility model and advantage will be with these explanations And become more apparent from, clearly.
Nuclear fuel element in current nuclear reactor is solid construction, during nuclear fission, nuclear fuel element The temperature of interior portion can be high.Because cooling agent passes through in nuclear fuel element outer surface, heat is unidirectional from core inner to outside Diffusion, cooling effect (heat transfer efficiency) is limited.If the inside of nuclear fuel element uses hollow-core construction, the hollow inside of nuclear fuel element With outer surface by cooling agent, the heat of generation can be transmitted inside and outside, then cooling effect can be greatly improved.This hair Person of good sense's research confirms that hollow nuclear fuel element has excellent nuclear fuel cooling effect, and it would is that following nuclear fuel element is set One of meter generation, the trend manufactured, with more wide application prospect.
Thus, as shown in figure 1, the utility model provides a kind of nuclear fuel element, the nuclear fuel element 100 includes shell Layer 1 and hypostracum 2, enclosed construction is formed between the outer shell 1 and hypostracum 2 to be used to load fuel pellet 3.
As shown in figure 1, nuclear fuel element 100 is tubular structure, its hypostracum 2 is internally formed hollow duct area 4, it is described in Cooling agent is passed to outside empty flow path area 4 and outer shell 1.
Nuclear fuel in fuel pellet 3 includes any one in fissile material uranium -235 or plutonium -239 or its combination, fission The content of material is 1 (weight) %~5.5 (weight) %, preferably 3.0 (weight) %~3.5 (weight) %.
In a preferred embodiment, as shown in FIG. 1 to 3, the main cross section of the nuclear fuel element 100 is symmetrical Any one in loop configuration, such as annular, square annular or isoceles triangle annular, preferably square annular.Wherein, annular is same Heart annulus.Square annular and isoceles triangle annular are similar with annular, and square annular refers to that inward flange and outward flange are the same of rectangle Heart loop configuration, wherein, the side of inner rectangular is parallel with the corresponding sides of outer rectangular.Isoceles triangle annular refers to inward flange and outer Edge is the annular concentric structure of isosceles triangle, wherein, the side of inside triangle is parallel with the corresponding sides of external triangular.
In further preferred embodiment, the length of the nuclear fuel element 100 is 20mm~250mm.
When nuclear fuel element 100 main cross section be annular when, its inner ring radius be 5~19mm, outer shroud radius be 6~ 20mm；
When the main cross section of nuclear fuel element 100 is annular for square, its inner ring length of side is respectively 10~38mm, 10~38mm； The outer shroud length of side is respectively 12~40mm, 12~40mm；
When the main cross section of nuclear fuel element 100 is annular for isoceles triangle, its inner ring length of side is respectively 16~64mm, 16 ~64mm and 16~64mm, the outer shroud length of side is respectively 18~66mm, 18~66mm and 18~66mm.
On the one hand the size of above-mentioned nuclear fuel element 100 can meet the reactor heap-type of various power to fuel element size Requirement, on the other hand can provide enough heat transfer spaces for hollow duct area 4, improve heat transfer efficiency.
In a preferred embodiment, as shown in Figure 4 and Figure 5, the outer shell 1 include separation layer I 11, it is described every Absciss layer I 11 is zircaloy, and alloying element includes any one or more in tin, niobium, iron, chromium or nickel.Preferably, separation layer I 11 Outer to be arranged radiation protection layer I 12, the radiation protection layer I 12 is steel radiation protection layer, boron radiation protection layer, lead radiation protection layer Or the steel radiation protection layer of doped carbon nanometer pipe.
In further preferred embodiment, the thickness of the separation layer I 11 is 0.5mm~0.8mm, radiation protection layer I 12 thickness is 0.5mm~0.8mm.The selection of separation layer I 11 and the thickness of radiation protection layer I 12 considers radiation protection simultaneously Effect and factor effectively of both transmission heat.If thickness is excessive, although Radioprotective Effect is strengthened, but its Transmission thermal resistance is inevitably enlarged, and rational thickness can ensure that radiation protection and heat transfer all reach ideal effect.
In another preferred embodiment, the hypostracum 2 includes separation layer II 21, and the separation layer II 21 is zirconium Alloy, alloying element includes any one or more in tin, niobium, iron, chromium or nickel.HTHP of the zircaloy at 300~400 DEG C There are good corrosion resisting property, moderate mechanical property, relatively low atom thermal neutron absorption cross section in water and steam, have to nuclear fuel Good compatibility, therefore, zircaloy can be used as the core structural material of reactor.Preferably, closely tied in separation layer II 21 Conjunction has radiation protection layer II 22, and the radiation protection layer II 22 is steel radiation protection layer, boron radiation protection layer, lead radiation protection layer Or the steel radiation protection layer of doped carbon nanometer pipe.
In further preferred embodiment, the thickness of the separation layer II 21 is 0.5mm~0.8mm, radiation protection The thickness of layer II 22 is 0.5mm~0.8mm.
When reactor operation, nuclear fission reaction will produce a large amount of neutrons and gamma-rays, and fission product decay also discharges α, β Particle and gamma-rays.α and β particle ranges are very short, it is easy to absorbed, operating personnel are not constituted by air or other objects typically Threaten；Neutron and gamma-rays have extremely strong penetration capacity, in order to stop that it is penetrated, and typically set concrete layer in reactor surrounding To be shielded.Occurs nuclear leakage in view of natural calamity or nuclear power plant equipment failure etc., concrete layer has been unable to reach The full purpose for completely cutting off and radiating.Radiation is respectively provided with the utility model in the hypostracum 2 and outer shell 1 of nuclear fuel element 100 anti- Sheath, further enhances the shielding to nuclear radiation.
In the utility model, as shown in fig. 6, the outside of outer shell 1 and the inner side of hypostracum 2 distribution bulge-structure, described interior Side refers to the direction towards hollow duct area 4.When outer shell 1 sets radiation protection layer I 12, and/or hypostracum 2 to set radiation anti- During sheath II 22, set on the inner surface of radiation protection layer II 22 on bulge-structure II 221, the outer surface of radiation protection layer I 12 Bulge-structure I 121 is set.To be easy to process, the bulge-structure I 121 and bulge-structure II 221 are arranged according to certain rules Simple geometry body.The bulge-structure I 121 and bulge-structure II 221 are appointed in cylinder, prism, cone or pyramid Meaning is one or more, individually a kind of preferably wherein.The height of bulge-structure I 121 and bulge-structure II 221 is 0.5~ 1.0mm.The selection of bulge-structure height has taken into full account that border turbulent flow mixes heat exchange and avoids the aspect of influence cooling agent flowing two The reason for.If bulge-structure is smaller, the effect that enhanced heat exchange is mixed on border is not had；But if bulge-structure is larger, Flow resistance can be then significantly increased, the proper flow of cooling agent is influenceed.
In a preferred embodiment, as shown in fig. 7, the bulge-structure is the square quadrangular in bottom surface, Its arrangement mode is closely to be arranged alternately.Close be arranged alternately refers to：Bulge-structure is on radiation protection layer along nuclear fuel Multirow is arranged on the length direction of element 100, the distance between bulge-structure is the length of side of bottom surface square, certain a line convexity The space between structure correspondence adjacent lines relief structure is played, i.e., adjacent protrusion structure shares a seamed edge in adjacent rows.Its In, the bottom surface of bulge-structure refers to the face in backward radiation overcoat direction.
Bulge-structure can effectively strengthen the flowing and heat exchange of cooling medium.When cooling agent is in hollow duct area 4 and core , can be with because cooling agent at different bulge-structure positions generates larger Turbulent Kinetic during 100 flows outside of fuel element The generation of laminar boundary layer effectively is prevented, and the secondary flow of the cooling agent thus formed can be sufficiently by nuclear fuel member Hot-fluid inside part 100 is taken away, and improves cooling effect.
In the utility model, the reactor heap-type that above-mentioned nuclear fuel element is applied is pressurized water reactor, and cooling agent is Water.The pressure of cooling agent is 8~25.5MPa, and it is within the scope of reactor entrance temperature is 150~280 DEG C, and outlet temperature is Within the scope of 450~530 DEG C, mass velocity is 600~2100kg/m2s。
Under the above parameters, the heat transfer coefficient of the nuclear fuel element of annular (main cross section) is 30~45kW/m2K, square The heat transfer coefficient of the nuclear fuel element of annular (main cross section) is 15~25kW/m2K, the nuclear fuel member of triangular ring (main cross section) The heat transfer coefficient of part is 5~12kW/m2·K.The nuclear fuel element coefficient of heat transfer efficiency of annular (main cross section) is most on the whole It is high.But pass through stress intensive analysis, if section is annular, it is vulnerable to extruding after its nuclear fuel element machine-shaping and becomes Shape, and crimp is not easily susceptible to after the annular machine-shaping of square, so the nuclear fuel element of square annular (main cross section) makes shaping After be more beneficial for industrialized production, and the nuclear fuel element heat transfer coefficient of square annular (main cross section) has met use demand, Thus, nuclear fuel element 100 is preferably the nuclear fuel element of square annular (main cross section).
Another aspect of the present utility model be to provide in a kind of nuclear fuel assembly, the nuclear fuel assembly it is parallel be fixed with it is many Individual nuclear fuel element 100 described above.Nuclear fuel element 100 is arranged into square in nuclear fuel assembly, its spread pattern (row × row) are 10*10~25*25, and the nuclear fuel assembly of square arrangement mode is conducive to producing the reality of nuclear fuel element Border arrangements of operations, form is not simply error-prone, and heat transfer efficiency is high.Distinguish on the top of all nuclear fuel elements 100 and bottom Install and be respectively provided with element interface 200 corresponding with nuclear fuel element 100 on upper cover and low head, upper cover and low head, on The element interface 200 of end socket is used for the hollow duct area 4 that cooling agent is injected separately into each nuclear fuel element 100, the member of low head Part interface 200 receives the cooling agent by hollow duct area 4.Meanwhile, apopore 300, upper envelope are set on upper cover and low head Cooling agent is passed through inside nuclear fuel assembly and the fluid interchange between nuclear fuel element 100 by the apopore 300 of head, low head Apopore 300 confluxes to cooling agent.So as to the hollow duct area 4 of nuclear fuel element 100 between nuclear fuel element 100 Interior circulation has cooling agent.
It is preferably carried out in one kind in mode, as shown in figure 8, on upper cover or low head, every four apopores 300 are equal Even to be distributed in around an element interface 200, every four element interfaces 200 are uniformly distributed in around an apopore 300.
In further preferred embodiment, nuclear fuel element 100 is arranged into square in nuclear fuel assembly, just Square corner and middle part is not provided with nuclear fuel element 100.This be due to edge corner be unfavorable for heat exchange, easily formed Dead angle；And the vacancy of middle part is easy to cooling agent to be flowed with nuclear fuel assembly.
In a preferred embodiment, as shown in figure 9, nuclear fuel element 100 is with 21*21 distribution form parallel Cloth is in nuclear fuel assembly, and the distance between adjacent two nuclear fuel elements 100 D is 5mm~20mm in colleague or same column.Institute State and refer to apart from D：On the section perpendicular to nuclear fuel element, the section of adjacent two nuclear fuel elements in colleague or same column Size between the center of gravity of figure subtracts the size inside two sections figure.
Another aspect of the present utility model is to provide a kind of pressurized water reactor, be provided with the pressurized water reactor it is multiple including Cooling agent is connected between the nuclear fuel assembly of above-mentioned nuclear fuel element 100, nuclear fuel assembly.
Embodiment
Embodiment 1
A kind of nuclear fuel element 100, it is surrounded the hollow tubular knot that main cross section is annular by hypostracum 2 and outer shell 1 Structure, the enclosed construction formed between hypostracum 2 and outer shell 1 loads the uranium dioxide ceramic core containing 3.2 (weight) %U-235 Pass through cooling water outside hollow duct area 4 and outer shell 1 inside block, hypostracum 2.Wherein, the length of nuclear fuel element 100 is 100mm, its inner ring radius is 10mm, and outer shroud radius is 15mm.
The hypostracum 2 of nuclear fuel element 100 includes separation layer II 21 and the spoke on its inside directly contacted with cooling water Penetrate overcoat II 22.The outer shell 1 of nuclear fuel element 100 includes separation layer I 11 and directly contacted with cooling water positioned at its outside Radiation protection layer I 12.The thickness of separation layer II 21 and separation layer I 11 is 0.8mm, radiation protection layer II 22 and radiation protection The thickness of layer I 12 is 0.5mm.
Heat transfer coefficient test analysis is carried out using above-mentioned nuclear fuel element 100, the pressure of cooling agent is 25.0MPa, its Reactor entrance temperature is 200 DEG C, and outlet temperature is 500 DEG C, and mass velocity is 1000kg/m2S, as a result shows, the coefficient of heat transfer For 38.25kW/m2·K。
Embodiment 2
A kind of nuclear fuel element 100, it surrounds hollow tubular knot of the main cross section for square annular by hypostracum 2 and outer shell 1 Structure, the enclosed construction formed between hypostracum 2 and outer shell 1 loads the uranium dioxide ceramic core containing 3.2 (weight) %U-235 Hollow duct area 4 and the outside of outer shell 1 inside block, the loadings be the same as Example 1 of ceramic UO pellet, hypostracum 2 is logical Supercooled water.Wherein, the length of nuclear fuel element 100 is 100mm, and its inner ring length of side is respectively 18mm and 18mm, the outer shroud length of side Respectively 20mm and 20mm.
The hypostracum 2 of nuclear fuel element 100 includes separation layer II 21 and the spoke on its inside directly contacted with cooling water Penetrate overcoat II 22.The outer shell 1 of nuclear fuel element 100 includes separation layer I 11 and directly contacted with cooling water positioned at its outside Radiation protection layer I 12.The thickness of separation layer II 21 and separation layer I 11 is 0.8mm, radiation protection layer II 22 and radiation protection The thickness of layer I 12 is 0.5mm.
Heat transfer coefficient test analysis is carried out using above-mentioned nuclear fuel element 100, the pressure of cooling agent is 25.0MPa, its Reactor entrance temperature is 200 DEG C, and outlet temperature is 490 DEG C, and mass velocity is 1000kg/m2S, as a result shows, the coefficient of heat transfer For 22.62kW/m2·K。
Embodiment 3
A kind of nuclear fuel element 100, it is surrounded the hollow tubular that main cross section is triangular ring by hypostracum 2 and outer shell 1 Structure, the enclosed construction formed between hypostracum 2 and outer shell 1 loads the uranium dioxide ceramic core containing 3.2 (weight) %U-235 Hollow duct area 4 and the outside of outer shell 1 inside block, the loadings be the same as Example 1 of ceramic UO pellet, hypostracum 2 is logical Supercooled water.Wherein, the length of nuclear fuel element 100 is 100mm, and its inner ring length of side is respectively 30mm, 30mm and 30mm, outer shroud The length of side is respectively 32mm, 32mm and 32mm.
The hypostracum 2 of nuclear fuel element 100 includes separation layer II 21 and the spoke on its inside directly contacted with cooling water Penetrate overcoat II 22.The outer shell 1 of nuclear fuel element 100 includes separation layer I 11 and directly contacted with cooling water positioned at its outside Radiation protection layer I 12.The thickness of separation layer II 21 and separation layer I 11 is 0.8mm, radiation protection layer II 22 and radiation protection The thickness of layer I 12 is 0.5mm.
Heat transfer coefficient test analysis is carried out using above-mentioned nuclear fuel element 100, the pressure of cooling agent is 25.0MPa, its Reactor entrance temperature is 200 DEG C, and outlet temperature is 508 DEG C, and mass velocity is 1000kg/m2S, as a result shows, the coefficient of heat transfer For 9.06kW/m2·K。
Embodiment 4
A kind of nuclear fuel element 100, it surrounds hollow tubular knot of the main cross section for square annular by hypostracum 2 and outer shell 1 Structure, the enclosed construction formed between hypostracum 2 and outer shell 1 loads the uranium dioxide ceramic core containing 3.2 (weight) %U-235 Hollow duct area 4 and the outside of outer shell 1 inside block, the loadings be the same as Example 1 of ceramic UO pellet, hypostracum 2 is logical Supercooled water.Wherein, the length of nuclear fuel element 100 is 100mm, and its inner ring length of side is respectively 18mm and 18mm, the outer shroud length of side Respectively 20mm and 20mm.
The hypostracum 2 of nuclear fuel element 100 includes separation layer II 21 and the spoke on its inside directly contacted with cooling water Penetrate overcoat II 22.The outer shell 1 of nuclear fuel element 100 includes separation layer I 11 and directly contacted with cooling water positioned at its outside Radiation protection layer I 12.The thickness of separation layer II 21 and separation layer I 11 is 0.8mm, radiation protection layer II 22 and radiation protection The thickness of layer I 12 is 0.5mm.
Bulge-structure is set on the inner surface of radiation protection layer II 22 and the outer surface of radiation protection layer I 12.Bulge-structure For the quadrangular that bottom surface is square, its arrangement mode is closely to be arranged alternately.
Heat transfer coefficient test analysis is carried out using above-mentioned nuclear fuel element 100, the pressure of cooling agent is 25.0MPa, its Reactor entrance temperature is 200 DEG C, and outlet temperature is 503 DEG C, and mass velocity is 1000kg/m2S, as a result shows, the coefficient of heat transfer For 25.1kW/m2·K。
Comparative example
Comparative example 1
A kind of nuclear fuel element, it is surrounded the tubular structure that main cross section is rectangle by involucrum, and the end of involucrum is close with plug Seal and the ceramic UO pellet containing 3.2 (weight) %U-235, the filling of ceramic UO pellet are loaded inside involucrum Measure be the same as Example 1.Pass through cooling water outside involucrum.Wherein, the length of nuclear fuel element is 100mm, the length of side point in involucrum section Wei not 20mm and 20mm.
Heat transfer coefficient test analysis is carried out using above-mentioned nuclear fuel element, the pressure of cooling agent is 25.0MPa, and it is in reaction Heap inlet temperature is 200 DEG C, and outlet temperature is 485 DEG C, and mass velocity is 1000kg/m2S, as a result shows, the coefficient of heat transfer is 7.31kW/m2·K。
, it is necessary to explanation, the orientation of the instruction such as term " on ", " under ", " interior ", " outer " in description of the present utility model Or position relationship is, based on the orientation or position relationship under utility model works state, to be for only for ease of and describe this practicality newly Type and simplified description, rather than instruction or the signified device of hint or element must be with specific orientation, with specific orientation Construction and operation, therefore it is not intended that to limitation of the present utility model.
Above in association with preferred embodiment the utility model is illustrated, but these embodiments are only models Example property, only play illustrative effect.On this basis, a variety of replacements and improvement can be carried out to the utility model, these Each fall within protection domain of the present utility model.

Claims (11)

1. a kind of nuclear fuel element, it is characterised in that the nuclear fuel element (100) includes outer shell (1) and hypostracum (2), Enclosed construction is formed between the outer shell (1) and hypostracum (2) to load fuel pellet (3), nuclear fuel element (100) is pipe Shape structure, its hypostracum (2) is internally formed outside hollow duct area (4), the hollow duct area (4) and outer shell (1) and passed to Cooling agent.
2. nuclear fuel element according to claim 1, it is characterised in that the main cross section of the nuclear fuel element (100) is Any one in annular, square annular or isoceles triangle annular.
3. nuclear fuel element according to claim 2, it is characterised in that the main cross section of the nuclear fuel element (100) is Square annular.
4. nuclear fuel element according to claim 1, it is characterised in that the main cross section of nuclear fuel element (100) is annulus Shape, its inner ring radius is 5~19mm, and outer shroud radius is 6~20mm.
5. nuclear fuel element according to claim 1, it is characterised in that the main cross section of nuclear fuel element (100) is square ring Shape, its inner ring length of side is respectively 10~38mm, 10~38mm；The outer shroud length of side is respectively 12~40mm, 12~40mm.
6. nuclear fuel element according to claim 1, it is characterised in that the main cross section of nuclear fuel element (100) is triangle Annular, its inner ring length of side is respectively 16~64mm, 16~64mm and 16~64mm, and the outer shroud length of side is respectively 18~66mm, 18 ~66mm and 18~66mm.
7. nuclear fuel element according to claim 1, it is characterised in that
The outer shell (1) includes being arranged radiation protection layer I (12) outside separation layer I (11), separation layer I (11),
The hypostracum (2), which includes combining closely in separation layer II (21), separation layer II (21), radiation protection layer II (22).
8. nuclear fuel element according to claim 1, it is characterised in that outer shell (1) is outside and hypostracum (2) inner side is divided Cloth bulge-structure, the bulge-structure in cylinder, prism, cone or pyramid any one or more.
9. nuclear fuel element according to claim 8, it is characterised in that the height of the bulge-structure is 0.5~ 1.0mm。
10. a kind of nuclear fuel assembly, it is characterised in that parallel fixation is just like one of claim 1~9 institute in the nuclear fuel assembly Circulated between the nuclear fuel element (100) stated, nuclear fuel element (100) and in the hollow duct area (4) of nuclear fuel element (100) There is cooling agent；
Nuclear fuel element (100) is arranged into square in nuclear fuel assembly.
11. a kind of pressurized water reactor, it is characterised in that multiple cores as claimed in claim 10 are provided with the pressurized water reactor Fuel assembly.
CN201621467758.7U 2016-12-29 2016-12-29 A kind of nuclear fuel element Expired - Fee Related CN206516360U (en)

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