CN106601311B - A kind of nuclear fuel element - Google Patents

A kind of nuclear fuel element Download PDF

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Publication number
CN106601311B
CN106601311B CN201611246847.3A CN201611246847A CN106601311B CN 106601311 B CN106601311 B CN 106601311B CN 201611246847 A CN201611246847 A CN 201611246847A CN 106601311 B CN106601311 B CN 106601311B
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nuclear fuel
fuel element
hypostracum
radiation protection
outer shell
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CN106601311A (en
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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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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/60Metallic fuel; Intermetallic dispersions
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18Emergency cooling arrangements; Removing shut-down heat
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • G21C3/08Casings; Jackets provided with external means to promote heat-transfer, e.g. fins, baffles
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Dispersion Chemistry (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention discloses a kind of nuclear fuel elements, the nuclear fuel element (100) includes outer shell (1) and hypostracum (2), and enclosed construction is formed between the outer shell (1) and hypostracum (2) to load fuel pellet (3);Nuclear fuel element (100) is tubular structure, forms hollow duct area (4) inside hypostracum (2), coolant is passed to outside the hollow duct area (4) and outer shell (1).Nuclear fuel element has hollow duct area in the present invention, by coolant inside and outside nuclear fuel element, greatly improves the heat transfer efficiency of nuclear fuel element, can effectively avoid the possibility that nuclear fuel element cooling effect deficiency causes accident.

Description

A kind of nuclear fuel element
Technical field
The present invention relates to nuclear energy source domain, more particularly to a kind of nuclear fuel element with inside and outside Double-protection structure.
Background technology
Nuclear fuel element is supporting substances indispensable in the application of modern society nuclear energy.In order to 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 Fuel element, the spherical nuclear fuel element etc. in forth generation high temperature gas cooled reactor.Even if can the heat in nuclear reactor effective It is taken away by coolant, is a very important Consideration in nuclear power station design, especially in the feelings that major accident occurs Under condition, the generation effectively taken away residual heat of nuclear core, reactor is avoided to melt the accidents such as heap is more needed.Nuclear fuel element internal high temperature Heat can not effectively cooled medium be taken away, and be the important problem that nuclear fuel element is faced.
Therefore, the present inventor studies nuclear fuel element, a kind of anti-suitable for core with high heat transfer intensity to provide Answer the nuclear fuel element of heap.
Invention content
To solve the above-mentioned problems, present inventor has performed sharp studies, as a result, it has been found that:Nuclear fuel element is carried out hollow It designs, by coolant inside and outside nuclear fuel element, greatly improves the heat transfer efficiency of nuclear fuel element, can effectively avoid core combustion Expect element in the case that major accident cooling capacity is insufficient, to occur to melt heap accident risk higher and after reactor shutdown Cannot residual heat of nuclear core be exported into problem encountered quickly, thereby completing the present invention.
The purpose of the present invention is to provide a kind of nuclear fuel element, the nuclear fuel element 100 includes outer shell 1 and inner casing Layer 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 2 inside of hypostracum forms hollow duct area 4, the hollow duct area 4 Coolant is passed to outside outer shell 1.
According to a kind of nuclear fuel element provided by the invention, have the advantages that:
(1) nuclear fuel element has hollow duct area in the present invention, by coolant inside and outside nuclear fuel element, greatly carries The high heat transfer efficiency of nuclear fuel element, can effectively avoid nuclear fuel element in the case that major accident occur to melt heap accident can It can property;
(2) bulge-structure is arranged on the shell contacted with coolant in the present invention, and coolant is made to form turbulent flow, can be effective The generation for preventing laminar boundary layer, and the resulting coolant Secondary Flow can be fully by the warm inside nuclear fuel element Stream is taken away, and heat transfer efficiency is improved;
(3) outer shell and hypostracum include separation layer and radiation protection layer in the present invention, further reduced nuclear leakage Risk;
(4) nuclear fuel element design principle is clear in the present invention, simple in structure, can effectively, economically by scale It manufactures, becomes a kind of safe and reliable nuclear fuel element.
Description of the drawings
Fig. 1 shows the main cross section structural schematic diagram of nuclear fuel element in the present invention;
Fig. 2 shows a kind of nuclear fuel element main cross section structural schematic diagrams of preferred embodiment in the present invention;
Fig. 3 shows the sectional view of nuclear fuel element line A-A along Fig. 2;
Fig. 4 shows raised structural schematic diagram on nuclear fuel element;
Fig. 5 shows in the present invention a kind of signal of raised Structural assignments mode on radiation protection layer in preferred embodiment Figure;
Fig. 6 shows point of element interface and water outlet on a kind of upper cover or low head of preferred embodiment in the present invention Cloth schematic diagram;
Fig. 7 shows a kind of arrangement mode signal of nuclear fuel assembly center fuel element in preferred embodiment in the present invention Figure.
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- water outlets.
Specific implementation mode
Present invention will now be described in detail, and the features and advantages of the invention will become more with these explanations It is clear, clear.
Nuclear fuel element in current nuclear reactor is solid construction, during nuclear fission, nuclear fuel element The temperature of interior portion can be high.Since coolant passes through in nuclear fuel element outer surface, heat is unidirectional from core inner to outside Diffusion, cooling effect (heat transfer efficiency) are limited.If the inside of nuclear fuel element uses hollow-core construction, the hollow inside of nuclear fuel element With outer surface by coolant, the heat of generation can transmit inside and outside, then cooling effect can be greatly improved.This hair A person of good sense, which studies, to be confirmed, hollow nuclear fuel element has excellent nuclear fuel cooling effect, will be the following nuclear fuel element and sets One of the trend that meter occurs, manufactures, has more wide application prospect.
Thus, as shown in Figure 1, the present invention provides a kind of nuclear fuel element, which includes outer shell 1 With hypostracum 2, enclosed construction is formed between the outer shell 1 and hypostracum 2 for loading fuel pellet 3.
As shown in figures 1 and 3, nuclear fuel element 100 is tubular structure, and 2 inside of hypostracum forms hollow duct area 4, Coolant is passed to outside the hollow duct area 4 and outer shell 1.
Nuclear fuel in fuel pellet 3 includes any one in fissile material uranium -235 or plutonium -239, and fissile material contains Amount is 1 (weight) %~5.5 (weight) %, preferably 3.0 (weight) %~3.5 (weight) %.
In a preferred embodiment, the main cross section of the nuclear fuel element 100 is symmetrical loop configuration, such as annulus Any one in shape, square annular or isoceles triangle annular, preferably square annular.Wherein, circular ring shape is donut.Square annular and Isoceles triangle annular is similar with circular ring shape, and square annular refers to inward flange and outer edge is the annular concentric structure of rectangle, 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 isoceles triangle The annular concentric structure of shape, 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 the main cross section of nuclear fuel element 100 be circular ring shape when, inner ring radius be 5~19mm, outer shroud radius be 6~ 20mm;
When the main cross section of nuclear fuel element 100 is square annular, the 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 isoceles triangle annular, the inner ring length of side is respectively 16~64mm, 16 ~64mm and 16~64mm, the outer shroud length of side are 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 be that hollow duct area 4 provide enough heat transfer spaces, improve heat transfer efficiency.
In a preferred embodiment, as shown in Figures 2 and 3, 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 I 12 thickness of separation layer I 11 and radiation protection layer considers radiation protection simultaneously Effect and factor effectively of both transmission heat.If thickness is excessive, although Radioprotective Effect is reinforced, its It transmits thermal resistance to inevitably enlarge, it is ideal that rational thickness can ensure that radiation protection and heat transfer all achieve the effect that.
In another preferred embodiment, the hypostracum 2 includes separation layer II 21, and the separation layer II 21 is zirconium Alloy, alloying element include any one or more in tin, niobium, iron, chromium or nickel.High temperature and pressure of the zircaloy at 300~400 DEG C There are good corrosion resisting property, moderate mechanical property, lower atom thermal neutron absorption cross section in water and steam, has to nuclear fuel Good compatibility, therefore, zircaloy can be used as the core structural material of reactor.Preferably, it is closely tied in separation layer II 21 It is steel radiation protection layer, boron radiation protection layer, lead radiation protection layer that conjunction, which has radiation protection layer II 22, the radiation protection layer II 22, 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 generate 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 be absorbed by air or other objects, not constituted to operating personnel generally It threatens;Neutron and gamma-rays have extremely strong penetration capacity, and in order to stop that it is penetrated, concrete layer generally is arranged in reactor surrounding To be shielded.Nuclear leakage occurs in view of natural calamity or nuclear power plant equipment failure etc., concrete layer has been unable to reach The full purpose completely cut off and radiate.It is respectively provided with radiation protection layer in the hypostracum 2 of nuclear fuel element 100 and outer shell 1 in the present invention, Further enhance the shielding to nuclear radiation.
In the present invention, as shown in figure 4,1 outside of outer shell and 2 inside of hypostracum are distributed bulge-structure, the inside is Refer to the direction towards hollow duct area 4.When radiation protection layer I 12 and/or the setting radiation protection layer of hypostracum 2 is arranged in outer shell 1 When II 22, bulge-structure II 221 is set on the inner surface of radiation protection layer II 22, is arranged on the outer surface of radiation protection layer I 12 Bulge-structure I 121.To be easy to process, the bulge-structure I 121 and bulge-structure II 221 be arrange according to certain rules it is simple Solid.The bulge-structure I 121 and bulge-structure II 221 are any one in cylinder, prism, cone or pyramid Kind is a variety of, individually a kind of preferably wherein.The height of bulge-structure I 121 and bulge-structure II 221 is 0.5~1.0mm.It is convex The selection for playing structure height has fully considered that boundary turbulent flow mixes heat exchange and avoids influencing reason of both coolant flowing.Such as When fruit bulge-structure is smaller, then the effect that enhanced heat exchange is mixed on boundary is not had;But if bulge-structure is larger, then can obviously increase Big flow resistance influences the proper flow of coolant.
In a preferred embodiment, as shown in figure 5, the bulge-structure is the square quadrangular in bottom surface, Its arrangement mode is closely to be arranged alternately.Close be arranged alternately refer to:Bulge-structure is in radiation protection layer upper edge 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 It plays structure and corresponds to the gap between adjacent rows relief structure, 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 protective layer direction.
Bulge-structure can effectively enhance the flowing and heat exchange of cooling medium.When coolant is in hollow duct area 4 and core It, can be with since coolant produces larger Turbulent Kinetic at different bulge-structure positions when 100 flows outside of fuel element The effective generation for preventing laminar boundary layer, and the secondary flow of the resulting coolant can be adequately by nuclear fuel member Hot-fluid inside part 100 is taken away, and cooling effect is improved.
In the present invention, the reactor heap-type that above-mentioned nuclear fuel element is applied is pressurized water reactor, and coolant is water.It is cold But the pressure of agent be 8~25.5MPa, reactor entrance temperature be 150~280 DEG C within the scope of, outlet temperature be 450~ Within the scope of 530 DEG C, mass velocity is 600~2100kg/m2s。
Under the above parameters, the heat transfer coefficient of the nuclear fuel element of circular ring shape (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 core combustion of isoceles triangle annular (main cross section) Expect that the heat transfer coefficient of element is 5~12kW/m2·K.On the whole, the nuclear fuel element coefficient of heat transfer effect of circular ring shape (main cross section) Rate highest.But pass through stress intensity and analyze, if section is circular ring shape, it is vulnerable to extruding after nuclear fuel element machine-shaping Deformation, and crimp is not easily susceptible to after square annular machine-shaping, so the nuclear fuel element of square annular (main cross section) is fabricated to Industrialized production is more advantageous to after type, and the nuclear fuel element heat transfer coefficient of square annular (main cross section) has met use and needed It asks, thus, nuclear fuel element 100 is preferably the nuclear fuel element of square annular (main cross section).
Another aspect of the present invention is to provide a kind of nuclear fuel assembly, parallel in the nuclear fuel assembly to be fixed on multiple State the nuclear fuel element 100.Nuclear fuel element 100 is arranged into square in nuclear fuel assembly, spread pattern (row × Row) it is 10*10~25*25, the nuclear fuel assembly of square arrangement mode is conducive to the practical operation for producing nuclear fuel element Arrangement, form is not simply error-prone, and heat transfer efficiency is high.
End socket and low head, upper cover and low head are installed respectively on the top of all nuclear fuel elements 100 and lower part On be respectively provided with element interface 200 corresponding with nuclear fuel element 100, the element interface 200 of upper cover is for distinguishing coolant The hollow duct area 4 of each nuclear fuel element 100 is injected, the element interface 200 of low head receives the cooling by hollow duct area 4 Agent.Meanwhile apopore 300 is set on upper cover and low head, coolant is passed through nuclear fuel assembly by the apopore 300 of upper cover Internal and the fluid interchange between nuclear fuel element 100, the apopore 300 of low head converge to coolant.To core combustion Circulating between material element 100 and in the hollow duct area 4 of nuclear fuel element 100 has coolant.
It is preferably carried out in mode in one kind, as shown in fig. 6, 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 Rectangular quadrangle and intermediate position are not provided with nuclear fuel element 100.This is because the corner at edge is unfavorable for exchanging heat, it is easy to be formed Dead angle;And the vacancy at intermediate position convenient for coolant with flowed in nuclear fuel assembly.
In a preferred embodiment, as shown in fig. 7, nuclear fuel element 100 is with the distribution form parallel of 21*21 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 Stating distance D refers to:On the section perpendicular to nuclear fuel element, colleague or same column in two adjacent nuclear fuel elements section Size between the center of gravity of figure subtracts the size inside two sections figure.
Another aspect of the present invention is to provide a kind of pressurized water reactor, and it includes above-mentioned to be provided in the pressurized water reactor multiple The nuclear fuel assembly of nuclear fuel element 100 is connected with coolant between nuclear fuel assembly.
Embodiment
Embodiment 1
A kind of nuclear fuel element 100 surrounds the hollow tubular knot that main cross section is circular ring shape by hypostracum 2 and outer shell 1 Structure, the enclosed construction formed between hypostracum 2 and outer shell 1 load the uranium dioxide ceramic core containing 3.2 (weight) %U-235 Block passes through cooling water outside the hollow duct area 4 and outer shell 1 inside hypostracum 2.Wherein, the length of nuclear fuel element 100 is 100mm, inner ring radius are 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 being in direct contact with cooling water Penetrate protective layer II 22.The outer shell 1 of nuclear fuel element 100 includes separation layer I 11 and is in direct contact 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 coolant is 25.0MPa, Reactor entrance temperature is 200 DEG C, and outlet temperature is 500 DEG C, mass velocity 1000kg/m2S, the results showed that, the coefficient of heat transfer For 38.25kW/m2·K。
Embodiment 2
A kind of nuclear fuel element 100 surrounds the hollow tubular knot that main cross section is square annular by hypostracum 2 and outer shell 1 Structure, the enclosed construction formed between hypostracum 2 and outer shell 1 load the uranium dioxide ceramic core containing 3.2 (weight) %U-235 Block, with embodiment 1, the hollow duct area 4 and 1 outside of outer shell inside hypostracum 2 are logical for the loadings of ceramic UO pellet Supercooled water.Wherein, the length of nuclear fuel element 100 is 100mm, and the 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 being in direct contact with cooling water Penetrate protective layer II 22.The outer shell 1 of nuclear fuel element 100 includes separation layer I 11 and is in direct contact 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 coolant is 25.0MPa, Reactor entrance temperature is 200 DEG C, and outlet temperature is 490 DEG C, mass velocity 1000kg/m2S, the results showed that, the coefficient of heat transfer For 22.62kW/m2·K。
Embodiment 3
A kind of nuclear fuel element 100 surrounds 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 load the uranium dioxide ceramic core containing 3.2 (weight) %U-235 Block, with embodiment 1, the hollow duct area 4 and 1 outside of outer shell inside hypostracum 2 are logical for the loadings of ceramic UO pellet Supercooled water.Wherein, the length of nuclear fuel element 100 is 100mm, and the 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 being in direct contact with cooling water Penetrate protective layer II 22.The outer shell 1 of nuclear fuel element 100 includes separation layer I 11 and is in direct contact 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 coolant is 25.0MPa, Reactor entrance temperature is 200 DEG C, and outlet temperature is 508 DEG C, mass velocity 1000kg/m2S, the results showed that, the coefficient of heat transfer For 9.06kW/m2·K。
Embodiment 4
A kind of nuclear fuel element 100 surrounds the hollow tubular knot that main cross section is square annular by hypostracum 2 and outer shell 1 Structure, the enclosed construction formed between hypostracum 2 and outer shell 1 load the uranium dioxide ceramic core containing 3.2 (weight) %U-235 Block, with embodiment 1, the hollow duct area 4 and 1 outside of outer shell inside hypostracum 2 are logical for the loadings of ceramic UO pellet Supercooled water.Wherein, the length of nuclear fuel element 100 is 100mm, and the 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 being in direct contact with cooling water Penetrate protective layer II 22.The outer shell 1 of nuclear fuel element 100 includes separation layer I 11 and is in direct contact 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, 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 coolant is 25.0MPa, Reactor entrance temperature is 200 DEG C, and outlet temperature is 503 DEG C, mass velocity 1000kg/m2S, the results showed that, the coefficient of heat transfer For 25.1kW/m2·K。
Comparative example
Comparative example 1
A kind of nuclear fuel element surrounds the tubular structure that main cross section is rectangle by involucrum, and the end plug of involucrum is close It seals and loads the ceramic UO pellet containing 3.2 (weight) %U-235, the filling of ceramic UO pellet inside involucrum Amount is the same as embodiment 1.Pass through cooling water outside involucrum.Wherein, the length of nuclear fuel element is 100mm, the length of side point in involucrum section It Wei not 20mm and 20mm.
Heat transfer coefficient test analysis is carried out using above-mentioned nuclear fuel element, the pressure of coolant is 25.0MPa, is being reacted Heap inlet temperature is 200 DEG C, and outlet temperature is 485 DEG C, mass velocity 1000kg/m2S, the results showed that, the coefficient of heat transfer is 7.31kW/m2·K。
In the description of the present invention, it should be noted that the orientation or position of the instructions such as term "upper", "lower", "inner", "outside" It is to be merely for convenience of the description present invention based on the orientation or positional relationship under working condition of the present invention and simplification is retouched to set relationship It states, does not indicate or imply the indicated device or element must have a particular orientation, with specific azimuth configuration and operation, Therefore it is not considered as limiting the invention.
Above in association with preferred embodiment, the present invention is described, but these embodiments are only exemplary , only play the role of illustrative.On this basis, a variety of replacements and improvement can be carried out to the present invention, these each fall within this In the protection domain of invention.

Claims (3)

1. a kind of nuclear fuel element, which is characterized 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 tubular structure, forms hollow duct area (4) inside hypostracum (2), the hollow duct area (4) and outside outer shell (1) coolant is passed to;
The outer shell (1) includes separation layer I (11), and radiation protection layer I (12) is arranged outside separation layer I (11), and the radiation is anti- Sheath I (12) is the steel radiation protection layer of doped carbon nanometer pipe;
The hypostracum (2) includes separation layer II (21), and combining closely in separation layer II (21) has radiation protection layer II (22), institute State the steel radiation protection layer that radiation protection layer II (22) is doped carbon nanometer pipe;
The main cross section of the nuclear fuel element (100) is symmetrical annular structure Moments annular;The main cross section of nuclear fuel element (100) is Square annular, the inner ring length of side is respectively 10~38mm, 10~38mm;The outer shroud length of side is respectively 12~40mm, 12~40mm;Shell Layer (1) is external and hypostracum (2) inside is distributed bulge-structure, and the bulge-structure is the square quadrangular in bottom surface, row Mode for cloth is closely to be arranged alternately;The height of the bulge-structure is 0.5~1.0mm.
2. a kind of nuclear fuel assembly, which is characterized in that parallel in the nuclear fuel assembly to be fixed with core combustion as described in claim 1 Expect element (100), between nuclear fuel element (100) and in the hollow duct area (4) of nuclear fuel element (100) circulation have cooling Agent.
3. nuclear fuel assembly according to claim 2, which is characterized in that nuclear fuel element (100) is in nuclear fuel assembly It is arranged into square.
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