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CN104766636B - A nested integrated structure of nuclear fuel rods and central cooling heat pipes - Google Patents

A nested integrated structure of nuclear fuel rods and central cooling heat pipes Download PDF

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Publication number
CN104766636B
CN104766636B CN201510188176.9A CN201510188176A CN104766636B CN 104766636 B CN104766636 B CN 104766636B CN 201510188176 A CN201510188176 A CN 201510188176A CN 104766636 B CN104766636 B CN 104766636B
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nuclear fuel
fuel rod
cooling heat
central cooling
heat pipe
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CN104766636A (en
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赵辉
陈红丽
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University of Science and Technology of China USTC
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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
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/334Assembling, maintenance or repair of the bundles
    • 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
    • G21C3/12Means forming part of the element for locating it within the reactor core
    • 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)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The invention discloses the nested integral structure that a kind of nuclear fuel rod cools down heat pipe with center, including center cooling heat pipe, the nuclear fuel rod of positive six face column structure, the evaporator section of central cooling tube is placed in the core bore in the middle part of the nuclear fuel rod.Central cooling tube is followed successively by the porous wick structure, liquid ring cavity, tube wall that central steam area, porosity are 0.69 from inside to outside.Central steam area includes evaporator section, adiabatic section, condensation segment successively from bottom to top in the axial direction, and the length of evaporator section is consistent with the length of nuclear fuel rod.The inside of nuclear fuel rod is that fuel pellet, outside are involucrum, and the tube wall of the evaporator section of center cooling heat pipe is designed with the involucrum on the inside of nuclear fuel rod core bore to be integrated.0.1mm gap is left between fuel pellet and involucrum.Compact in design, safe, good reliability, are particularly suitable for use in nuclear reactor for space and the small-sized nuclear reactor of other specific uses.

Description

一种核燃料棒与中心冷却热管的嵌套一体化结构A nested integrated structure of nuclear fuel rods and central cooling heat pipes

技术领域technical field

本发明涉及一种核电能源技术,尤其涉及一种核燃料棒与中心冷却热管的嵌套一体化结构。The invention relates to nuclear power energy technology, in particular to a nested integrated structure of nuclear fuel rods and central cooling heat pipes.

背景技术Background technique

随着世界各国深空探测计划的开展与实施,未来在月球及其他星球表面进行空间基地建设将具有重大的科学、军事和政治价值。要在月球及其他星球表面建立空间基地,首先需要解决的是能源问题。而太阳能电池和同位素电池等方式难以空间基地满足大功率的实际需求,因此空间核反应堆在未来空间基地能源供应方面的优势明显。With the development and implementation of deep space exploration programs around the world, the construction of space bases on the surface of the moon and other planets in the future will have great scientific, military and political value. To establish space bases on the surface of the moon and other planets, the first thing that needs to be solved is the energy problem. However, solar cells and isotope batteries are difficult for space bases to meet the actual demand for high power. Therefore, space nuclear reactors have obvious advantages in the energy supply of future space bases.

美国、俄罗斯、日本等国均对空间核反应堆产生了浓厚的兴趣,研究并提出了数十种空间核反应堆系统方案,冷却方式包括热管冷却、液态金属冷却、气体冷却等。由于空间基地环境的复杂性,空间核反应堆堆芯应采取非能动冷却技术,热管冷却具有最优的热瞬态反馈性能、最优的可靠性、最低的保养需求,因此目前空间核反应堆设计大都采用热管冷却,燃料棒所产生的热量由冷却热管带出堆芯,再通过能量转换系统提供能源供应。The United States, Russia, Japan and other countries have all developed a strong interest in space nuclear reactors, researched and proposed dozens of space nuclear reactor system solutions, cooling methods include heat pipe cooling, liquid metal cooling, gas cooling, etc. Due to the complexity of the space base environment, the core of space nuclear reactors should adopt passive cooling technology. Heat pipe cooling has the best thermal transient feedback performance, the best reliability, and the lowest maintenance requirements. Therefore, most current space nuclear reactor designs use heat pipes. Cooling, the heat generated by the fuel rods is taken out of the core by the cooling heat pipe, and then provided with energy supply through the energy conversion system.

如图3a所示,在现有的空间核反应堆设计中,燃料棒与冷却热管被制作成外径相同的圆柱状,采用燃料棒与冷却热管的相邻布置方式。但是,这种布置方式由于受到热管几何形状的约束,燃料棒与热管之间必然存在间隙,造成燃料填充率较低,而燃料棒与冷却热管之间的间隙通过结构材料进行填充后,导致核反应堆临界质量以及堆芯总质量的增大。As shown in Figure 3a, in the existing space nuclear reactor design, the fuel rods and cooling heat pipes are made into cylindrical shapes with the same outer diameter, and the fuel rods and cooling heat pipes are arranged adjacently. However, due to the constraints of the geometric shape of the heat pipes in this arrangement, there must be a gap between the fuel rods and the heat pipes, resulting in a low fuel filling rate, and the gap between the fuel rods and the cooling heat pipes is filled with structural materials, resulting in a nuclear reactor. Critical mass and increase in total core mass.

发明内容Contents of the invention

本发明的目的是提供一种布局紧凑、安全性高、可靠性好的核燃料棒与中心冷却热管的嵌套一体化结构。The object of the present invention is to provide a nested integrated structure of nuclear fuel rods and central cooling heat pipes with compact layout, high safety and good reliability.

本发明的目的是通过以下技术方案实现的:The purpose of the present invention is achieved through the following technical solutions:

本发明的核燃料棒与中心冷却热管的嵌套一体化结构,包括中心冷却热管、核燃料棒,所述中心冷却管的蒸发段置于所述核燃料棒中部的芯孔中。The nested integrated structure of nuclear fuel rods and central cooling heat pipes of the present invention includes central cooling heat pipes and nuclear fuel rods, and the evaporation section of the central cooling pipes is placed in the core hole in the middle of the nuclear fuel rods.

由上述本发明提供的技术方案可以看出,本发明实施例提供的核燃料棒与中心冷却热管的嵌套一体化结构,由于中心冷却管的蒸发段置于所述核燃料棒中部的芯孔中,布局紧凑、安全性高、可靠性好,特别适用于空间核反应堆以及其他特殊用途的小型核反应堆。It can be seen from the above-mentioned technical solution provided by the present invention that in the nested integrated structure of the nuclear fuel rod and the central cooling heat pipe provided by the embodiment of the present invention, since the evaporation section of the central cooling pipe is placed in the core hole in the middle of the nuclear fuel rod, With compact layout, high safety and good reliability, it is especially suitable for space nuclear reactors and other small nuclear reactors for special purposes.

附图说明Description of drawings

图1为本发明实施例提供的核燃料棒与中心冷却热管的嵌套一体化结构的径向截面结构示意图;Fig. 1 is a schematic diagram of a radial cross-sectional structure of a nested integrated structure of a nuclear fuel rod and a central cooling heat pipe provided by an embodiment of the present invention;

图2为本发明实施例提供的核燃料棒与中心冷却热管的嵌套一体化结构的轴向截面结构示意图;Figure 2 is a schematic diagram of an axial cross-sectional structure of a nested integrated structure of a nuclear fuel rod and a central cooling heat pipe provided by an embodiment of the present invention;

图3a为现有技术中堆芯所采用的核燃料棒与冷却热管布置示意图;Figure 3a is a schematic diagram of the arrangement of nuclear fuel rods and cooling heat pipes used in the prior art;

图3b为本发明实施例提供的核燃料棒与中心冷却热管的嵌套一体化结构应用于堆芯设计的布置示意图。Fig. 3b is a schematic layout diagram of the nested integrated structure of nuclear fuel rods and central cooling heat pipes applied to the core design provided by the embodiment of the present invention.

图中:In the picture:

1、燃料芯块,2、包壳,3、液态环腔,4、多孔吸液芯,5、中心蒸汽区,6、蒸发段,7、绝热段,8、冷凝段,9、核燃料棒,10、中心冷却热管(或冷却热管)。1. Fuel pellets, 2. Cladding, 3. Liquid annular cavity, 4. Porous liquid-absorbing core, 5. Central vapor zone, 6. Evaporation section, 7. Insulation section, 8. Condensation section, 9. Nuclear fuel rod, 10. Central cooling heat pipe (or cooling heat pipe).

具体实施方式detailed description

下面将对本发明实施例作进一步地详细描述。The embodiments of the present invention will be further described in detail below.

本发明的核燃料棒与中心冷却热管的嵌套一体化结构,其较佳的具体实施方式是:The nested integrated structure of the nuclear fuel rod and the central cooling heat pipe of the present invention, its preferred embodiment is:

包括中心冷却热管、核燃料棒,所述中心冷却管的蒸发段置于所述核燃料棒中部的芯孔中。It includes a central cooling heat pipe and a nuclear fuel rod, and the evaporation section of the central cooling pipe is placed in a core hole in the middle of the nuclear fuel rod.

所述中心冷却管自内向外依次为中心蒸汽区、多孔吸液芯、液态环腔、管壁。The central cooling pipe consists of a central steam area, a porous liquid-absorbing core, a liquid annular cavity, and a pipe wall from the inside to the outside.

所述中心蒸汽区在轴向上自底部到顶部依次包括蒸发段、绝热段、冷凝段,所述蒸发段的长度与核燃料棒的长度一致。The central steam zone includes an evaporation section, an adiabatic section, and a condensation section sequentially from the bottom to the top in the axial direction, and the length of the evaporation section is consistent with the length of the nuclear fuel rod.

所述多孔吸液芯的孔隙率为0.69。The porosity of the porous wick was 0.69.

所述核燃料棒的内部为燃料芯块、外部为包壳,所述中心冷却热管的蒸发段的管壁与所述核燃料棒芯孔内侧的包壳设计为一体。The inside of the nuclear fuel rod is a fuel pellet, and the outside is a cladding, and the tube wall of the evaporation section of the central cooling heat pipe is integrated with the cladding inside the core hole of the nuclear fuel rod.

所述燃料芯块与所述包壳之间留有0.1mm的间隙。A gap of 0.1 mm is left between the fuel pellets and the cladding.

所述核燃料棒为正六面柱体结构。The nuclear fuel rod is a regular hexahedron structure.

本发明的核燃料棒与中心冷却热管的嵌套一体化结构,克服了现有技术中的缺点,布局紧凑、安全性高、可靠性好,特别适用于空间核反应堆以及其他特殊用途的小型核反应堆。这种核燃料棒与中心冷却热管的嵌套一体化结构可以在反应堆堆芯紧密布置,有效地提高堆芯的燃料填充度,减小堆芯的临界质量,从而可以减少结构材料、屏蔽材料的使用,降低堆芯的总质量;同时,热管布置相对密度增加,可以有效避免单根热管失效所引发的问题,可靠性高。本发明实现了核燃料棒与中心冷却热管的嵌套一体化结构设计,采用的非能动紧凑设计,可有效提高反应堆的安全性和可靠性。The nested integrated structure of nuclear fuel rods and central cooling heat pipes of the present invention overcomes the shortcomings of the prior art, and has compact layout, high safety and good reliability, and is especially suitable for space nuclear reactors and other small nuclear reactors for special purposes. The nested integrated structure of nuclear fuel rods and central cooling heat pipes can be closely arranged in the reactor core, effectively increasing the fuel filling degree of the core, reducing the critical mass of the core, thereby reducing the use of structural materials and shielding materials , reducing the total mass of the core; at the same time, the relative density of the heat pipe arrangement is increased, which can effectively avoid the problems caused by the failure of a single heat pipe, and has high reliability. The invention realizes the nested integrated structure design of nuclear fuel rods and central cooling heat pipes, adopts a passive compact design, and can effectively improve the safety and reliability of the reactor.

中心冷却热管蒸发段吸收燃料芯块产生的热量,并经过中心冷却热管绝热段和冷凝段将热量带出堆芯。燃料芯块与包壳之间留有0.1mm的间隙可以收纳裂变气体。The evaporation section of the central cooling heat pipe absorbs the heat generated by the fuel pellets, and takes the heat out of the core through the adiabatic section and the condensation section of the central cooling heat pipe. A gap of 0.1 mm is left between the fuel pellet and the cladding to accommodate fission gas.

与现有的技术相比,本发明的有益效果是:Compared with prior art, the beneficial effect of the present invention is:

(1)核燃料棒为正六面柱体可紧凑布置,从而提高燃料填充度,降低核反应堆临界质量,减小堆芯体积。(1) The nuclear fuel rods are regular hexahedrons and can be compactly arranged, thereby increasing the fuel filling degree, reducing the critical mass of the nuclear reactor, and reducing the core volume.

(2)减少了结构材料、屏蔽材料的使用,降低堆芯质量。(2) The use of structural materials and shielding materials is reduced, and the core quality is reduced.

(3)热管布置相对密度增加,能够有效避免单根热管失效所引发的问题,可靠性高。(3) The relative density of heat pipe arrangement is increased, which can effectively avoid problems caused by the failure of a single heat pipe, and has high reliability.

具体实施例:Specific examples:

以应用于空间核反应堆堆芯设计为例,核燃料棒与中心冷却热管的设计寿命均以堆芯寿期为参考,在堆芯寿期内无需更换。Taking the core design of a space nuclear reactor as an example, the design life of nuclear fuel rods and central cooling heat pipes is based on the core life, and there is no need to replace them during the core life.

如附图1、2所示,中心冷却热管10置于核燃料棒9中心,中心冷却热管蒸发段6与核燃料棒长度一致,中心冷却热管蒸发段6吸收燃料芯块1产生的热量,并经过中心冷却热管绝热段7和冷凝段8将热量带出堆芯。核燃料棒9内为燃料芯块1,核燃料棒9外为燃料棒包壳2。燃料芯块与包壳之间留有0.1mm的间隙以收纳裂变气体。中心冷却热管外壳与核燃料棒内包壳设计为一体,管内为孔隙率为0.69的多孔吸液芯4,吸液芯与管壁之间为液态环腔3,热管中心部位为中心蒸汽区5。As shown in accompanying drawings 1 and 2, the central cooling heat pipe 10 is placed in the center of the nuclear fuel rod 9, and the evaporation section 6 of the central cooling heat pipe is consistent with the length of the nuclear fuel rod. The evaporation section 6 of the central cooling heat pipe absorbs the heat generated by the fuel pellet 1 and passes through the center Cooling heat pipe adiabatic section 7 and condensing section 8 take heat out of the core. Inside the nuclear fuel rod 9 is a fuel pellet 1 , and outside the nuclear fuel rod 9 is a fuel rod cladding 2 . A gap of 0.1 mm is left between the fuel pellet and the cladding to accommodate fission gas. The shell of the central cooling heat pipe is integrated with the inner cladding of the nuclear fuel rod. Inside the tube is a porous liquid-absorbing core 4 with a porosity of 0.69.

本发明应用于空间核反应堆堆芯设计的效果如图3b所示,燃料棒与冷却热管的布局相对于如图3a所示的现有技术中的堆芯设计更加紧凑,提高了燃料填充率,降低核反应堆临界质量,减小堆芯体积,同时也减少了结构材料、屏蔽材料的使用,降低堆芯质量。而且,热管布置相对密度增加,能够有效避免单根热管失效所引发的问题,可靠性高。The effect of the present invention applied to the core design of a space nuclear reactor is shown in Figure 3b. The layout of fuel rods and cooling heat pipes is more compact than the core design in the prior art shown in Figure 3a, which improves the fuel filling rate and reduces The critical mass of the nuclear reactor reduces the volume of the core, and also reduces the use of structural materials and shielding materials, reducing the quality of the core. Moreover, the relative density of heat pipe arrangement increases, which can effectively avoid problems caused by failure of a single heat pipe, and has high reliability.

本发明未详细阐述的部分属于本领域的公知技术。The parts not described in detail in the present invention belong to the known technology in the art.

以上所述,仅为本发明较佳的具体实施方式,但本发明的保护范围并不局限于此,任何熟悉本技术领域的技术人员在本发明披露的技术范围内,可轻易想到的变化或替换,都应涵盖在本发明的保护范围之内。因此,本发明的保护范围应该以权利要求书的保护范围为准。The above is only a preferred embodiment of the present invention, but the scope of protection of the present invention is not limited thereto. Any person familiar with the technical field can easily conceive of changes or changes within the technical scope disclosed in the present invention. Replacement should be covered within the protection scope of the present invention. Therefore, the protection scope of the present invention should be determined by the protection scope of the claims.

Claims (3)

1.一种核燃料棒与中心冷却热管的嵌套一体化结构,其特征在于,包括中心冷却热管、核燃料棒,所述中心冷却管的蒸发段置于所述核燃料棒中部的芯孔中;1. A nested integrated structure of a nuclear fuel rod and a central cooling heat pipe, characterized in that it includes a central cooling heat pipe and a nuclear fuel rod, and the evaporation section of the central cooling pipe is placed in the core hole in the middle of the nuclear fuel rod; 所述中心冷却管自内向外依次为中心蒸汽区、多孔吸液芯、液态环腔、管壁;The central cooling pipe is sequentially composed of a central steam area, a porous liquid-absorbing core, a liquid annular cavity, and a pipe wall from the inside to the outside; 所述中心蒸汽区在轴向上自底部到顶部依次包括蒸发段、绝热段、冷凝段,所述蒸发段的长度与核燃料棒的长度一致;The central steam zone includes an evaporation section, an adiabatic section, and a condensation section sequentially from the bottom to the top in the axial direction, and the length of the evaporation section is consistent with the length of the nuclear fuel rod; 所述核燃料棒的内部为燃料芯块、外部为包壳,所述中心冷却热管的蒸发段的管壁与所述核燃料棒芯孔内侧的包壳设计为一体;The inside of the nuclear fuel rod is a fuel pellet, and the outside is a cladding, and the tube wall of the evaporation section of the central cooling heat pipe is designed as one with the cladding inside the core hole of the nuclear fuel rod; 所述核燃料棒为正六面柱体结构。The nuclear fuel rod is a regular hexahedron structure. 2.根据权利要求1所述的核燃料棒与中心冷却热管的嵌套一体化结构,其特征在于,所述多孔吸液芯的孔隙率为0.69。2. The nested integrated structure of nuclear fuel rods and central cooling heat pipes according to claim 1, characterized in that the porosity of the porous liquid-absorbing core is 0.69. 3.根据权利要求1或2所述的核燃料棒与中心冷却热管的嵌套一体化结构,其特征在于,所述燃料芯块与所述包壳之间留有0.1mm的间隙。3. The nested integrated structure of nuclear fuel rods and central cooling heat pipes according to claim 1 or 2, characterized in that there is a gap of 0.1 mm between the fuel pellets and the cladding.
CN201510188176.9A 2015-04-20 2015-04-20 A nested integrated structure of nuclear fuel rods and central cooling heat pipes Expired - Fee Related CN104766636B (en)

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