CN108511092A - A kind of integral structure that nuclear fuel element is nested with circuit parallel type cooling heat pipe - Google Patents
A kind of integral structure that nuclear fuel element is nested with circuit parallel type cooling heat pipe Download PDFInfo
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/24—Promoting flow of the coolant
- G21C15/257—Promoting flow of the coolant using heat-pipes
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/18—Emergency cooling arrangements; Removing shut-down heat
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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
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- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
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- Y02E30/30—Nuclear fission reactors
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Abstract
Description
技术领域technical field
本发明涉及核能发电技术领域,具体涉及一种核燃料元件与回路并行式冷却热管嵌套的一体化结构。The invention relates to the technical field of nuclear power generation, in particular to an integrated structure in which nuclear fuel elements and loop parallel cooling heat pipes are nested.
背景技术Background technique
随着太空探索技术的不断发展成熟与太空探索应用需求的扩大,人类已将目光放到了远离地球甚至远离太阳系的星球,并希望在星球上建设太空基地进行相关的科学研究。未来在其他星球表面(如月球、火星等)进行空间基地的建设,将具有十分重大的科学、军事和政治价值。空间基地的建设面临着复杂、严峻的空间环境,能源的稳定供应与管理成为空间基地正常运行的重要保障。太阳能电源和化学能电源因为自身的固有缺陷,无法克服如昼夜变化、燃料储量的一些因素的影响,使其在空间基地上的应用受到很大的局限。空间核反应堆电源不受环境影响、功率大、寿命长、安全可靠、能源供应可持续性强,因此被认为是空间基地与其他深空探测任务中理想可靠的能源供应方案。With the continuous development and maturity of space exploration technology and the expansion of space exploration application requirements, human beings have set their sights on planets far away from the earth or even the solar system, and hope to build space bases on the planets to conduct related scientific research. In the future, the construction of space bases on the surface of other planets (such as the moon, Mars, etc.) will have very important scientific, military and political values. The construction of space bases is faced with a complex and severe space environment, and the stable supply and management of energy has become an important guarantee for the normal operation of space bases. Due to their own inherent defects, solar power and chemical energy power cannot overcome the influence of some factors such as day and night changes and fuel reserves, so their application on space bases is greatly limited. The space nuclear reactor power supply is not affected by the environment, has high power, long life, safety and reliability, and strong energy supply sustainability. Therefore, it is considered to be an ideal and reliable energy supply solution for space bases and other deep space exploration missions.
由于空间核反应堆在空间基地与其他深空探测任务中具有许多无法替代的优势,美国、俄罗斯、日本、法国等国对空间核反应堆进行了诸多深入的研究,并提出了数十种空间核反应堆方案,其冷却方式包括气体冷却、液态金属冷却、热管冷却等。由于空间基地环境的复杂性,非能动冷却技术是空间核反应堆的首选,而热管冷却技术是具有高热导率、高瞬态反馈性能、高可靠性、低保养需求等优点的非能动冷却技术,因此目前空间核反应堆设计大都采用热管冷却。Because space nuclear reactors have many irreplaceable advantages in space bases and other deep space exploration missions, the United States, Russia, Japan, France and other countries have conducted many in-depth studies on space nuclear reactors and proposed dozens of space nuclear reactor solutions. Cooling methods include gas cooling, liquid metal cooling, heat pipe cooling, etc. Due to the complexity of the space base environment, passive cooling technology is the first choice for space nuclear reactors, and heat pipe cooling technology is a passive cooling technology with advantages such as high thermal conductivity, high transient feedback performance, high reliability, and low maintenance requirements. Therefore, At present, space nuclear reactor designs are mostly cooled by heat pipes.
在现有空间核反应堆设计中,单根冷却热管被布置在燃料元件中,在堆芯径向布置上,现有的布置方式有的会导致燃料元件与热管之间存在间隙,造成燃料填充率较低,而燃料元件与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及堆芯总质量的增大;有的会对单根热管的可靠性提出很高的要求,一旦有一根热管失效,该热管处的核燃料元件所产生的热量很难被周围的热管带走,可能会导致核燃料元件的损坏。In the existing space nuclear reactor design, a single cooling heat pipe is arranged in the fuel element. In the radial arrangement of the core, some of the existing arrangements will cause a gap between the fuel element and the heat pipe, resulting in a low fuel filling rate. low, and the gap between the fuel element and the heat pipe is filled with structural materials, resulting in an increase in the critical mass of the nuclear reactor and the total mass of the core; some will place high requirements on the reliability of a single heat pipe, once a If the heat pipe fails, the heat generated by the nuclear fuel element at the heat pipe is difficult to be taken away by the surrounding heat pipes, which may cause damage to the nuclear fuel element.
发明内容Contents of the invention
本发明的目的是针对现有技术的不足,提供了一种安全性高、可靠性好、布局紧凑的核燃料元件与回路并行式冷却热管嵌套的一体化结构。The object of the present invention is to address the deficiencies of the prior art and provide an integrated structure in which nuclear fuel elements and circuit parallel cooling heat pipes are nested with high safety, good reliability and compact layout.
本发明的目的可以通过如下技术方案实现:The purpose of the present invention can be achieved through the following technical solutions:
一种核燃料元件与回路并行式冷却热管嵌套的一体化结构,包括核燃料元件和冷却热管,冷却热管置于核燃料元件中心,且相邻的两个核燃料元件中心的冷却热管的两端采用U型弯头连接,形成回路并行式。An integrated structure in which nuclear fuel elements and loop parallel cooling heat pipes are nested, including nuclear fuel elements and cooling heat pipes, the cooling heat pipes are placed in the center of the nuclear fuel elements, and the two ends of the cooling heat pipes at the center of the adjacent two nuclear fuel elements are U-shaped Elbow connection to form a loop parallel.
进一步地,所述冷却热管自内向外依次为中心蒸汽区、多孔吸液芯、液态环腔和管壁,其中管壁与核燃料元件的内侧包壳设计为一体。Further, the cooling heat pipe includes a central steam area, a porous liquid-absorbing core, a liquid annular cavity, and a pipe wall from inside to outside, wherein the pipe wall and the inner cladding of the nuclear fuel element are designed as one.
进一步地,所述多孔吸液芯的孔隙率为0.5至0.7。Further, the porosity of the porous liquid-absorbent core is 0.5 to 0.7.
进一步地,所述冷却热管的中心蒸汽区在轴向上自底部到顶部依次包括蒸发段、绝热段和冷凝段,且相邻两个冷却热管中心蒸汽区的蒸发段底部采用蒸发段U型弯头连接,冷凝段顶部采用冷凝段U型弯头连接。Further, the central steam area of the cooling heat pipe includes an evaporation section, an adiabatic section and a condensation section in the axial direction from the bottom to the top, and the bottom of the evaporation section of the central steam area of two adjacent cooling heat pipes adopts a U-shaped bend of the evaporation section The top of the condensation section is connected by a U-shaped elbow in the condensation section.
进一步地,所述核燃料元件的内部为燃料芯块,外部为包壳,所述冷却热管的蒸发段长度与核燃料元件的高度一致。Further, the inside of the nuclear fuel element is a fuel pellet, and the outside is a cladding, and the length of the evaporation section of the cooling heat pipe is consistent with the height of the nuclear fuel element.
进一步地,所述燃料芯块与所述包壳之间留有0.1至0.3mm的间隙。Further, there is a gap of 0.1 to 0.3 mm between the fuel pellet and the cladding.
进一步地,所述核燃料元件是底面为正方形的长方体结构,或者底面为正六边形的六棱柱结构。Further, the nuclear fuel element is a cuboid structure with a square base, or a hexagonal prism structure with a regular hexagon base.
本发明与现有技术相比,具有如下优点和有益效果:Compared with the prior art, the present invention has the following advantages and beneficial effects:
1、本发明提供的一种核燃料元件与回路并行式冷却热管嵌套的一体化结构,由于采用回路式并行热管,在加热段或者冷凝段热流密度不均衡时,管内部的工作液体在通道内部产生整体形式循环,蒸发段热流密度大的一侧产生的蒸汽压力较大,推动蒸汽向热流密度小压力低的一侧,整个环路最终达到一个自激平衡的状态,回路式并行热管结构,可以在较大范围内自动调节换热能力,安全性高、可靠性好。1. The present invention provides an integrated structure in which nuclear fuel elements and loop parallel cooling heat pipes are nested. Due to the use of loop parallel heat pipes, when the heat flux density in the heating section or condensation section is unbalanced, the working liquid inside the tube is in the channel. The overall form of circulation is generated, and the steam pressure generated on the side with high heat flux density in the evaporation section is relatively high, pushing the steam to the side with low heat flux density and low pressure, and the whole loop finally reaches a state of self-excited balance. The loop-type parallel heat pipe structure, The heat exchange capacity can be automatically adjusted in a wide range, with high safety and reliability.
2、本发明提供的核燃料元件与回路并行式冷却热管嵌套的一体化结构,将回路并行式冷却热管与核燃料元件嵌套在一起,所述核燃料元件是底面为正方形的长方体结构,或者底面为正六边形的六棱柱结构,可以在堆芯中紧密布置,从而提高核燃料填充率,减小堆芯体积,降低临界质量,这种结构安全性高、可靠性好、布局紧凑,特别适用于空间核反应堆以及其他的小型核反应堆。2. The integrated structure of the nuclear fuel element and the loop parallel cooling heat pipe nested by the present invention nests the loop parallel cooling heat pipe and the nuclear fuel element together. The nuclear fuel element is a rectangular parallelepiped structure with a square bottom, or a bottom surface of The regular hexagonal hexagonal prism structure can be closely arranged in the core, thereby increasing the nuclear fuel filling rate, reducing the core volume, and reducing the critical mass. This structure has high safety, good reliability, and compact layout, and is especially suitable for space nuclear reactors and other small nuclear reactors.
附图说明Description of drawings
图1为本发明实施例核燃料元件与回路并行式冷却热管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-section of a nested integrated structure of a nuclear fuel element and a circuit parallel cooling heat pipe according to an embodiment of the present invention.
图2为本发明实施例核燃料元件与回路并行式冷却热管嵌套一体化结构的轴向截面结构示意图。Fig. 2 is a schematic diagram of an axial cross-sectional structure of a nested integrated structure of a nuclear fuel element and a circuit parallel cooling heat pipe according to an embodiment of the present invention.
图3(a)为本发明实施例核燃料元件与回路并行式冷却热管嵌套一体化结构应用于反应堆堆芯的径向截面布置示意图;图3(b)为本发明实施例核燃料元件与回路并行式冷却热管嵌套一体化结构应用于反应堆堆芯的轴向截面布置示意图。Fig. 3 (a) is a radial cross-sectional layout diagram of a nuclear fuel element and a loop parallel cooling heat pipe nesting integrated structure applied to a reactor core in an embodiment of the present invention; Fig. 3 (b) is a schematic diagram of a nuclear fuel element and a loop in parallel in an embodiment of the present invention Schematic diagram of the axial cross-sectional layout of the integrated cooling and heat pipe nesting structure applied to the reactor core.
图4为现有技术中单根冷却热管被布置在燃料元件中的结构示意图。Fig. 4 is a structural schematic view of a single cooling heat pipe arranged in a fuel element in the prior art.
图5为现有技术中单根冷却热管被布置在燃料元件中的一种堆芯径向布置示意图。Fig. 5 is a schematic diagram of a core radial arrangement in which a single cooling heat pipe is arranged in a fuel element in the prior art.
图6为现有技术中单根冷却热管被布置在燃料元件中的另一种堆芯径向布置示意图。Fig. 6 is a schematic diagram of another core radial arrangement in which a single cooling heat pipe is arranged in a fuel element in the prior art.
其中,1-燃料芯块,2-包壳,3-液态环腔,4-多孔吸液芯,5-蒸发段,6-绝热段,7-冷凝段,8-蒸发段U型弯头,9-冷凝段U型弯头,10-核燃料元件,11-冷却热管。Among them, 1- fuel pellets, 2- cladding, 3- liquid ring cavity, 4- porous liquid-absorbing core, 5- evaporation section, 6- adiabatic section, 7- condensation section, 8- U-shaped elbow in evaporation section, 9-U-shaped elbow in the condensation section, 10-nuclear fuel element, 11-cooling heat pipe.
具体实施方式Detailed ways
下面结合实施例及附图对本发明作进一步详细的描述,但本发明的实施方式不限于此。The present invention will be further described in detail below in conjunction with the embodiments and the accompanying drawings, but the embodiments of the present invention are not limited thereto.
实施例:Example:
本实施例以应用于空间核反应堆堆芯设计为例,核燃料元件与冷却热管的设计寿命与堆芯寿期一致,在堆芯寿期内无需更换,提供了一种核燃料元件与回路并行式冷却热管嵌套的一体化结构,所述结构的径向截面和轴向截面分别如图1和图2所示,包括核燃料元件(10)和冷却热管(11),冷却热管(11)置于核燃料元件(10)中心,且相邻的两个核燃料元件(10)中心的冷却热管(11)的两端采用U型弯头连接,形成回路并行式,相比于图4所示的现有技术中单根冷却热管被布置在燃料元件中的结构,回路式并行热管结构可以在较大范围内自动调节换热能力,安全性高、可靠性好。This embodiment is applied to the core design of a space nuclear reactor as an example. The design life of the nuclear fuel element and the cooling heat pipe is consistent with the core life, and there is no need to replace it during the core life. A parallel cooling heat pipe for the nuclear fuel element and the circuit is provided. A nested integrated structure, the radial section and axial section of the structure are shown in Figure 1 and Figure 2 respectively, including a nuclear fuel element (10) and a cooling heat pipe (11), and the cooling heat pipe (11) is placed on the nuclear fuel element (10) center, and the two ends of the cooling heat pipes (11) in the center of two adjacent nuclear fuel elements (10) are connected by U-shaped elbows to form a parallel loop, compared to the prior art shown in Figure 4 The structure in which a single cooling heat pipe is arranged in the fuel element, and the loop-type parallel heat pipe structure can automatically adjust the heat exchange capacity in a wide range, with high safety and reliability.
其中,所述冷却热管(11)自内向外依次为中心蒸汽区、多孔吸液芯(4)、液态环腔(3)和管壁,其中管壁与核燃料元件(10)的内侧包壳设计为一体,所述多孔吸液芯(4)的孔隙率为0.5至0.7。Wherein, the cooling heat pipe (11) is sequentially composed of a central steam region, a porous liquid-absorbing core (4), a liquid annular cavity (3) and a pipe wall from the inside to the outside, wherein the pipe wall and the inner cladding of the nuclear fuel element (10) are designed As a whole, the porosity of the porous liquid-absorbent core (4) is 0.5 to 0.7.
具体地,所述冷却热管(11)的中心蒸汽区在轴向上自底部到顶部依次包括蒸发段(5)、绝热段(6)和冷凝段(7),且相邻两个冷却热管(11)中心蒸汽区的蒸发段底部采用蒸发段U型弯头(8)连接,冷凝段顶部采用冷凝段U型弯头(9)连接。Specifically, the central vapor zone of the cooling heat pipe (11) includes an evaporation section (5), an adiabatic section (6) and a condensation section (7) in the axial direction from the bottom to the top, and two adjacent cooling heat pipes ( 11) The bottom of the evaporation section in the central steam zone is connected by a U-shaped elbow (8) in the evaporation section, and the top of the condensation section is connected by a U-shaped elbow (9) in the condensation section.
所述核燃料元件(10)的内部为燃料芯块(1),外部为包壳(2),所述冷却热管(11)的蒸发段(5)长度与核燃料元件(10)的高度一致,所述燃料芯块(1)与所述包壳(2)之间留有0.1至0.3mm的间隙。冷却热管(11)中心蒸汽区的蒸发段(5)吸收燃料芯块(1)产生的热量,经过绝热段(6)后,在冷凝段(7)将热量传动给其他工作介质,燃料芯块(1)与包壳(2)之间的间隙,用以容纳芯块膨胀和收纳裂变气体。The inside of the nuclear fuel element (10) is a fuel pellet (1), and the outside is a cladding (2), and the length of the evaporation section (5) of the cooling heat pipe (11) is consistent with the height of the nuclear fuel element (10), so A gap of 0.1 to 0.3 mm is left between the fuel pellet (1) and the cladding (2). The evaporating section (5) in the central steam area of the cooling heat pipe (11) absorbs the heat generated by the fuel pellets (1), and after passing through the adiabatic section (6), transfers the heat to other working media in the condensation section (7), and the fuel pellets The gap between (1) and the cladding (2) is used to accommodate the expansion of the pellet and to accommodate the fission gas.
具体地,所述核燃料元件(10)是底面为正方形的长方体结构,或者底面为正六边形的六棱柱结构。Specifically, the nuclear fuel element (10) is a cuboid structure with a square bottom surface, or a hexagonal prism structure with a regular hexagon bottom surface.
本实施例应用于空间核反应堆堆芯设计的示意图如图3(a)和图3(b)所示,相比于现有技术中图5和图6所示的堆芯布局方式,整个堆芯布局紧凑,可以在堆芯中紧密布置,从而提高核燃料填充率,减小堆芯体积,降低临界质量。冷却热管置于核燃料元件中心,且相邻的两个燃料元件中心的冷却热管的两端采用U型弯头连接,形成回路并行式,可以在较大范围内自动调节换热能力,能够有效避免因单根热管失效所引发的问题,可靠性高。The schematic diagram of this embodiment applied to the core design of a space nuclear reactor is shown in Figure 3 (a) and Figure 3 (b). Compared with the core layout shown in Figure 5 and Figure 6 in the prior art, the entire core The layout is compact and can be closely arranged in the core, thereby increasing the filling rate of nuclear fuel, reducing the volume of the core, and reducing the critical mass. The cooling heat pipe is placed in the center of the nuclear fuel element, and the two ends of the cooling heat pipe in the center of the two adjacent fuel elements are connected by a U-shaped elbow to form a parallel circuit, which can automatically adjust the heat exchange capacity in a wide range, and can effectively avoid The problem caused by the failure of a single heat pipe has high reliability.
以上所述,仅为本发明专利较佳的实施例,但本发明专利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专利所公开的范围内,根据本发明专利的技术方案及其发明专利构思加以等同替换或改变,都属于本发明专利的保护范围。The above is only a preferred embodiment of the patent of the present invention, but the scope of protection of the patent of the present invention is not limited thereto. The equivalent replacement or change of the technical solution and its invention patent concept all belong to the protection scope of the invention patent.
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| CN110211709A (en) * | 2019-06-14 | 2019-09-06 | 北京卫星环境工程研究所 | Heat pipe-type alkali metal converts integral reactor |
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| CN111081393A (en) * | 2019-12-31 | 2020-04-28 | 中国核动力研究设计院 | Integrated solid reactor core structure adopting heat pipe and fuel rod |
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