WO2024174372A1 - 一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置 - Google Patents

一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置 Download PDF

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Publication number
WO2024174372A1
WO2024174372A1 PCT/CN2023/090143 CN2023090143W WO2024174372A1 WO 2024174372 A1 WO2024174372 A1 WO 2024174372A1 CN 2023090143 W CN2023090143 W CN 2023090143W WO 2024174372 A1 WO2024174372 A1 WO 2024174372A1
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WIPO (PCT)
Prior art keywords
fuel
ball
fuel ball
outlet
unloading system
Prior art date
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Ceased
Application number
PCT/CN2023/090143
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English (en)
French (fr)
Inventor
吴寿贵
王轶
张瑞祥
李长海
令彤彤
姚尧
刘俊峰
康祯
胡杨
韩传高
董雷
马晓珑
高美
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Xian Thermal Power Research Institute Co Ltd
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Xian Thermal Power Research Institute Co Ltd
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Priority to DE112023005201.8T priority Critical patent/DE112023005201T5/de
Publication of WO2024174372A1 publication Critical patent/WO2024174372A1/zh
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

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Classifications

    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B07—SEPARATING SOLIDS FROM SOLIDS; SORTING
    • B07B—SEPARATING SOLIDS FROM SOLIDS BY SIEVING, SCREENING, SIFTING OR BY USING GAS CURRENTS; SEPARATING BY OTHER DRY METHODS APPLICABLE TO BULK MATERIAL, e.g. LOOSE ARTICLES FIT TO BE HANDLED LIKE BULK MATERIAL
    • B07B13/00—Grading or sorting solid materials by dry methods, not otherwise provided for; Sorting articles otherwise than by indirectly controlled devices
    • B07B13/04—Grading or sorting solid materials by dry methods, not otherwise provided for; Sorting articles otherwise than by indirectly controlled devices according to size
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/26—Arrangements for removing jammed or damaged fuel elements or control elements; Arrangements for moving broken parts thereof
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B07—SEPARATING SOLIDS FROM SOLIDS; SORTING
    • B07B—SEPARATING SOLIDS FROM SOLIDS BY SIEVING, SCREENING, SIFTING OR BY USING GAS CURRENTS; SEPARATING BY OTHER DRY METHODS APPLICABLE TO BULK MATERIAL, e.g. LOOSE ARTICLES FIT TO BE HANDLED LIKE BULK MATERIAL
    • B07B13/00—Grading or sorting solid materials by dry methods, not otherwise provided for; Sorting articles otherwise than by indirectly controlled devices
    • B07B13/14—Details or accessories
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/07—Pebble-bed reactors; Reactors with granular fuel
    • 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

Definitions

  • the present application belongs to the technical field of screening devices, and in particular relates to a fuel element fragment screening device for a high-temperature gas-cooled reactor nuclear power fuel loading and unloading system.
  • High temperature gas-cooled reactor nuclear power generation is the fourth generation of nuclear power generation system. Its design concept is that it will not cause core melting, large-scale radioactive material release, and no emergency measures are required outside the plant under extreme accident conditions. In the context of energy shortage and carbon reduction goals, it has unique development advantages and broad development prospects.
  • the fourth generation of high temperature gas-cooled reactor is a brand-new system, and there is no experience in many system designs and operations. It needs to be continuously verified and improved during the test and operation of the demonstration project.
  • the purpose of this application is to provide a fuel element fragment of a high temperature gas-cooled reactor nuclear power fuel loading and unloading system.
  • the screening device is used to solve the problem of baffle cutting balls during the operation of the fuel loading and unloading system and improve the reliability of the loading and unloading system.
  • a fuel element fragment screening device for a high temperature gas-cooled reactor nuclear power fuel loading and unloading system comprises a box body, a spiral screening track, a fuel ball inlet, a fuel ball outlet and a waste outlet; the box body is arranged on a baffle inlet pipe, a fuel ball inlet is arranged on the top of the box body, and a fuel ball outlet and a waste outlet are arranged on the bottom of the box body; inside the box body, a spiral screening damping track is arranged between the fuel ball inlet and the fuel ball outlet, the spiral screening pipe is in an inclined state, and the waste outlet is located below the spiral screening pipe.
  • the inclination angle of the spiral screening track is 45° to 80°, and the straight-line length of the vertical projection of the distance between the inlet and outlet of the spiral screening track on the plane is greater than or equal to the diameter of three fuel balls;
  • the plane projection diameter of the spiral screening track ring is 5 mm smaller than the diameter of the fuel ball, and the straight-line distance between any two rings of the spiral screening pipeline is 85% of the diameter of the fuel ball.
  • spiral screening intervals are evenly arranged on the spiral screening track, and the screening intervals are used to screen fuel balls and graphite dust with diameters less than 80%.
  • a guide bell mouth is arranged on the top of the fuel ball outlet, and the outlet of the spiral screening track is connected to the guide bell mouth.
  • an electromagnetic choke switch is provided on the fuel ball outlet.
  • a buffer hopper and a nuclear fuel ball fragment buffer tank are arranged above the waste outlet; the buffer hopper is connected to the top of the nuclear fuel ball fragment buffer tank, and the waste outlet is connected to the bottom of the nuclear fuel ball fragment buffer tank.
  • an isolation valve is provided at the connection between the buffer hopper and the nuclear fuel ball fragment buffer tank.
  • the isolation valve is composed of two circular steel plates, one above the other, with an "8"-shaped hole in the middle of each steel plate.
  • the steel plates are connected to a driving device, and the channel is opened when the two holes between the two steel plates overlap, and the channel is closed when they are staggered.
  • a discharge valve is provided at the connection between the waste outlet and the nuclear fuel ball fragment buffer tank, and the structure of the discharge valve is the same as that of the isolation valve.
  • the nuclear fuel ball fragment buffer tank is provided with a material level measuring element, a pressure measuring element and a connecting pipeline, and a vacuum valve is provided on the connecting pipeline; a pipeline is provided between the waste outlet and the fuel ball outlet, and a first valve and a second valve are provided on the pipeline.
  • an inspection hole is provided on the box body.
  • the present application provides a high temperature gas cooled reactor nuclear power fuel loading and unloading system for screening fuel ball fragments.
  • the device can completely separate intact fuel balls from fuel ball fragments, graphite dust and graphite ball fragments when the fuel balls, fuel ball fragments and dust mixture pass through the device during operation, effectively preventing the fragments and dust from entering the baffle and affecting the normal operation of the baffle, thereby improving the reliability of the fuel loading and unloading system.
  • FIG1 is a schematic diagram of the structure of the screening device of the present application.
  • FIG. 2 is a top view of the isolation valve of the present application.
  • Figure 3 is a diagram showing the connection between the device and the system.
  • FIG4 is a schematic diagram of a baffle.
  • orientations or positional relationships indicated by the terms “center”, “upper”, “lower”, “left”, “right”, “vertical”, “horizontal”, “inner”, “outer”, etc. are based on the orientations or positional relationships shown in the drawings, and are only for the convenience of describing the present application and simplifying the description, rather than indicating or implying that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and therefore cannot be understood as limiting the present application.
  • the terms “first”, “second”, and “third” are only used for descriptive purposes and cannot be understood as indicating or implying relative importance.
  • the terms “installed”, “connected”, and “connected” should be understood in a broad sense, for example, it can be a fixed connection, a detachable connection, or an integral connection; it can be a mechanical connection or an electrical connection; it can be a direct connection, or it can be indirectly connected through an intermediate medium, or it can be the internal communication of two components.
  • installed should be understood in a broad sense, for example, it can be a fixed connection, a detachable connection, or an integral connection; it can be a mechanical connection or an electrical connection; it can be a direct connection, or it can be indirectly connected through an intermediate medium, or it can be the internal communication of two components.
  • a fuel ball fragment screening device for a high temperature gas-cooled reactor nuclear power fuel loading and unloading system is shown in Figure 1.
  • the fuel ball fragment screening device is installed on the baffle inlet pipeline of the nuclear fuel loading and unloading system and is connected in series with the baffle on the same pipeline.
  • the fragment screening device When the system is put into operation normally, fuel balls, fuel ball fragments and Before the graphite dust enters the baffle, it first enters the fragment screening device, which separates the intact fuel balls from the fuel ball fragments and graphite dust to ensure that the fuel ball fragments and graphite dust do not enter the baffle.
  • the inlet pipeline of the flow control device of the nuclear fuel loading and unloading system is disconnected, and a box 003 with a volume of more than 0.3 cm3 is installed at the disconnected part of the pipeline.
  • the box 003 is provided with a fuel ball inlet 001, a fuel ball outlet 006 and a waste outlet 013.
  • a spiral screening track 004 is arranged between the fuel ball inlet 001 and the fuel ball outlet 006. One end of the spiral screening track is connected to the fuel ball inlet 001, and the other end is connected to the fuel ball outlet 006, forming a screening channel in the box 003.
  • the spiral screening pipeline 004 is designed to have an inclined angle of 45 to 80 degrees, and the straight length of the distance between the inlet and outlet projected vertically on the plane is greater than or equal to the diameter of three fuel balls 002; the plane projection diameter of the circular ring of the spiral screening track 004 is less than 5 mm of the fuel ball diameter, and the straight distance between any two rings of the channel is 85% of the fuel ball diameter, so as to ensure that larger fragments can pass through.
  • the designed pressure bearing capacity of box 003 is greater than 9MPa, and an inspection hole 022 is provided on the box to facilitate inspection of the situation inside the box during maintenance.
  • the fuel ball 002 When the device is put into operation, the fuel ball 002, its fragments and the graphite dust 020 produced by flow wear in the core enter the spiral screening track 004 from the fuel ball inlet 001.
  • the fuel ball 002, its fragments and the graphite dust 020 produced by flow wear in the core are mixed and separated into two paths after passing through the spiral screening pipe 004.
  • One path is the undamaged fuel ball or the fuel ball 002 which is not seriously damaged and will not cause other fuel balls to be cut after entering the baffle, passes through the guide bell mouth 005, enters the fuel ball outlet 006, and then enters the baffle.
  • an electromagnetic baffle switch 007 is designed at the fuel ball outlet 006.
  • the electromagnetic baffle switch works to block the fuel ball 002.
  • the electromagnetic baffle switch stops working and releases the fuel ball 002 to ensure the normal operation of the baffle.
  • the other fuel that is screened is fuel ball fragments and graphite dust 020 with a diameter less than 80%, which fall into the buffer hopper 021 after being screened by the spiral pipe 004, and enter the nuclear fuel ball fragment buffer tank 010 for buffering through the isolation valve 008, and then enter the waste fuel discharge pipeline 013 through the discharge valve 011, and finally discharged into the spent fuel storage system pipeline.
  • An isolation valve 008 is designed at the bottom of the buffer hopper 021.
  • the isolation valve 008 is connected to the buffer hopper 021 at the top and to the nuclear fuel ball fragment buffer tank 010 at the bottom. After the isolation valve 008 is opened, the separated fuel ball fragments and graphite dust 020 can fall into the buffer hopper 021 for temporary storage.
  • Design isolation door 008 is composed of two circular steel plates, one above and one below, with a There are 8-shaped holes, as shown in Figure 2.
  • the edge of the upper steel plate is provided with a driving gear, which is driven by a pneumatic or electric drive device 009 when it needs to be closed or opened.
  • the upper steel plate can rotate in both directions within a range of 90 degrees.
  • the channel is opened, and nuclear waste and graphite dust can directly enter the nuclear fuel ball fragment buffer tank 010 from the buffer bucket 021.
  • the channel is closed, and nuclear waste and graphite dust are prohibited from directly entering the nuclear fuel ball fragment buffer tank 010 from the buffer bucket 021.
  • the upper part of the nuclear fuel ball fragment buffer tank 010 is connected to the isolation valve 008, and the lower part is connected to the discharge valve 011.
  • a material level measuring element 019 is designed at the upper end of the nuclear fuel ball fragment buffer tank 010. When the material level rises and the material level measuring element 019 reaches a certain height, the system executes the discharge program to discharge the fragments inside the nuclear fuel ball fragment buffer tank 010 and the graphite dust 020 to the waste discharge pipe 013.
  • a discharge valve 011 is designed under the nuclear fuel pellet fragment buffer tank 010.
  • the upper part is connected to the nuclear fuel pellet fragment buffer tank 010, and the lower part is connected to the spent fuel discharge pipeline.
  • Its structure is the same as that of the isolation valve 008, and is composed of two circular steel plates, each with an "8"-shaped hole in the middle, as shown in FIG2.
  • a driving gear is provided on the edge of the upper steel plate, which is driven by a pneumatic or electric drive device 009 when it needs to be closed or opened.
  • the upper steel plate can rotate in both directions within a range of 90 degrees. When the two holes between the two steel plates overlap, the channel is opened, and nuclear waste and graphite dust can directly enter the waste discharge pipeline 013 from the nuclear fuel pellet fragment buffer tank 010. When the two holes between the two steel plates do not overlap, the channel is closed, and nuclear waste and graphite dust are prohibited from entering the waste discharge pipeline 013 from the nuclear fuel pellet fragment buffer tank 010.
  • the feed control valve and discharge control of the nuclear fuel ball fragment buffer tank 010 must be executed according to the procedure, that is, before the isolation valve 008 is opened to discharge to the nuclear fuel ball fragment buffer tank 010, the discharge valve 011 must be closed, the second valve 017 between the nuclear fuel ball fragment buffer tank 010 and the waste discharge pipeline 013 must be closed, the first valve 015 between the nuclear fuel ball fragment buffer tank 010 and the fuel ball outlet pipeline 006 must be closed, the vacuum valve 023 of the nuclear fuel ball fragment buffer tank 010 must be closed, the first valve 015 must be opened, and the isolation valve 008 must be opened when the pressure of the pressure measuring element 024 rises and is balanced with the system pressure. Under normal operating conditions, the isolation valve 008 remains open. When the material level signal 019 is issued, the isolation valve 008 is closed and the discharge procedure is carried out.
  • the system executes the discharge procedure, that is, closing the isolation valve 008 and the second valve between the nuclear fuel pellet fragment buffer tank 010 and the waste discharge pipeline 013. 017 is closed, the first valve 015 between the nuclear fuel ball fragment buffer tank 010 and the fuel ball outlet pipeline 006 is closed, and the vacuum valve 023 of the nuclear fuel ball fragment buffer tank 010 is opened.
  • the vacuum valve 23 is closed and the isolation valve 011 is opened to discharge the fragments and graphite dust 020 to the spent fuel discharge pipeline 013 and then transport them to the spent fuel storage tank.
  • the isolation valve 008 is closed, the second valve 017 between the nuclear fuel ball fragment buffer tank 010 and the waste discharge pipeline 013 is closed, the first valve 015 between the nuclear fuel ball fragment buffer tank 010 and the fuel ball outlet pipeline 006 is closed, the vacuum valve 023 of the nuclear fuel ball fragment buffer tank 010 is closed, the second valve 017 is opened, and when the pressure drop of the pressure measuring element 024 is balanced with the pressure of the waste discharge pipeline 013, the isolation valve 011 is opened to discharge the fragments and graphite dust 020 to the spent fuel discharge pipeline 013, and then transported to the spent fuel storage tank.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置，包括箱体、螺旋筛分管道、燃料球进口、燃料球出口和废料出口；箱体设置在阻流器进口管道上，箱体的顶部设置有燃料球进口，底部设置有燃料球出口和废料出口；在箱体的内部，燃料球进口和燃料球出口之间设置有螺旋筛分管道，且螺旋筛分管道为倾斜状态，废料出口位于螺旋筛分管道的下方。本申请在投运过程中，当燃料球、燃料球碎片及粉尘混合物通过装置后，装置能将完好无损的燃料球与燃料球碎片、石墨粉尘及石墨球碎片完全分离，有效阻止碎片及粉尘进入阻流器而影响阻流器的正常工作，提高燃料装卸系统的正常运行，提高系统运行的可靠性。

Description

一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置
相关申请的交叉引用
本申请要求在2023年2月21日提交中国专利局、申请号为202310147568.5、发明名称为“一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置”的中国专利申请的优先权，其全部内容通过引用的方式并入本文中。
技术领域
本申请属于筛分装置技术领域，特别涉及一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置。
背景技术
高温气冷堆核能发电是第四代核能发电系统，其设计理念是在极端事故工况下不造成堆芯融化、不发生大规模放射性物质释放、厂外不需应急措施等固有的物理安全特性在能源紧缺以及减碳目标的大环境下具有得天独厚的发展优势，具有广阔的发展前景。但是，第四代高温气冷堆是一个全新的系统，较多的系统设计及运行无经验可鉴，需要在示范项目试验和运行过程中不断的验证和完善。在核燃料装卸系统阻流器设计中未考虑到燃料球碎片及石墨粉尘对阻流器工作的影响，造成在实际运行过程中切球，导致燃料球破裂，将燃料球中UO2爆露在一回路中，增加一回路中粉尘的辐射济量，同时产生辐射济量较大的大量核废料，造成不必要燃料损耗以及高昂的核废料处理费用。然而在系统正常运行的情况下，在高温环境中，一回路介质的扰动以及加注燃料球过程中发生碰磨产生的碎片及粉尘沿卸球管道进入阻流器，导致阻流器切球，导致燃料球严重破损，使燃料装卸系统无法正常运行，严重制约高温堆热试的推进。
发明内容
本申请的目的在于提供一种高温气冷堆核电燃料装卸系统燃料元件碎片 筛分装置，以解决燃料装卸系统在运行过程中阻流器切球问题，提高装卸料系统的可靠性。
为实现上述目的，本申请采用以下技术方案：
一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置，包括箱体、螺旋筛分轨道、燃料球进口、燃料球出口和废料出口；箱体设置在阻流器进口管道上，箱体的顶部设置有燃料球进口，底部设置有燃料球出口和废料出口；在箱体的内部，燃料球进口和燃料球出口之间设置有螺旋筛分阻尼轨道，且螺旋筛分管道为倾斜状态，废料出口位于螺旋筛分管道的下方。
进一步的，螺旋筛分轨道的倾斜角度为45°到80°，并且螺旋筛分轨道进出口的距离垂直投影在平面上的直线长度大于等于三个燃料球的直径；螺旋筛分轨道圆环的平面投影直径小于燃料球直径5mm，螺旋筛分管道任两环间的直线距离为燃料球直径的85％。
进一步的，螺旋筛分轨道上均匀设置螺旋筛分间隔，筛分间隔用于筛分直径小于80％的燃料球与石墨粉尘。
进一步的，燃料球出口的顶部设置有导流喇叭口，螺旋筛分轨道的出口连接导流喇叭口。
进一步的，燃料球出口上还设置有电磁阻流开关。
进一步的，废料出口的上方设置有缓冲斗和核燃料球碎片缓冲罐；缓冲斗连接在核燃料球碎片缓冲罐的顶部，废料出口连接在核燃料球碎片缓冲罐的底部。
进一步的，缓冲斗和核燃料球碎片缓冲罐的连接处设置有隔离阀，隔离阀由上下两块圆形的钢板组成，钢板中间分别开有一个“8”字形孔；钢板连接有驱动装置，当两块钢板之间两孔有重叠时通道打开，交错时通道关闭。
进一步的，废料出口和核燃料球碎片缓冲罐的连接处设置有排放阀，排放阀的结构和隔离阀结构相同。
进一步的，核燃料球碎片缓冲罐上设置有料位测量元件、压力测量元件和连通管路，连通管路上设置有抽真空阀；废料出口和燃料球出口之间设置有管路，管路上设置有第一阀门和第二阀门。
进一步的，箱体上设置有检查孔。
与现有技术相比，本申请有以下技术效果：
本申请提供本申请一种高温气冷堆核电燃料装卸系堆燃料球碎片的筛分 装置，在装置投运过程中，当燃料球、燃料球碎片及粉尘混合物通过装置后，装置能将完好无损的燃料球与燃料球碎片、石墨粉尘及石墨球碎片完全分离，有效阻止碎片及粉尘进入阻流器而影响阻流器的正常工作，提高燃料装卸系统的可靠性。
附图说明
图1为本申请筛分装置图结构示意图。
图2为本申请隔离阀俯视结构图。
图3为装置与系统连接图。
图4为阻流器示意图。
具体实施方式
下面将结合附图对本申请的技术方案进行清楚、完整地描述，显然，所描述的实施例是本申请一部分实施例，而不是全部的实施例。基于本申请中的实施例，本领域普通技术人员在没有做出创造性劳动前提下所获得的所有其他实施例，都属于本申请保护的范围。
在本申请的描述中，需要说明的是，如出现术语“中心”、“上”、“下”、“左”、“右”、“竖直”、“水平”、“内”、“外”等指示的方位或位置关系为基于附图所示的方位或位置关系，仅是为了便于描述本申请和简化描述，而不是指示或暗示所指的装置或元件必须具有特定的方位、以特定的方位构造和操作，因此不能理解为对本申请的限制。此外，如出现术语“第一”、“第二”、“第三”仅用于描述目的，而不能理解为指示或暗示相对重要性。
在本申请的描述中，需要说明的是，除非另有明确的规定和限定，如出现术语“安装”、“相连”、“连接”应做广义理解，例如，可以是固定连接，也可以是可拆卸连接，或一体地连接；可以是机械连接，也可以是电连接；可以是直接相连，也可以通过中间媒介间接相连，可以是两个元件内部的连通。对于本领域的普通技术人员而言，可以具体情况理解上述术语在本申请中的具体含义。
请参阅图1至图4，一种高温气冷堆核电燃料装卸系燃料球碎片筛分装置如图1所示，核燃料装卸系统的阻流器进口管道加装燃料球碎片筛分装置，与阻流器串联在同一根管道上。当系统正常投运，燃料球、燃料球碎片以及 石墨粉尘进入阻流器前先进入碎片筛分装置，筛分装置将完整无损的燃料球与燃料球碎片、石墨粉尘分离，保证燃料球碎片和石墨粉尘不进入阻流器。
如图1所示在核燃料装卸系统的阻流器进口管道断开，在管道断开处加装一个容积为0.3厘方厘米以上的箱体003，在箱体003上设有燃料球进口001，燃料球出口006和废料出口013。在燃料球进口001与燃料球出口006之间布置一根螺旋筛分轨道004，螺旋筛分轨道一端与燃料球进口001相连，另一端与燃料球出口006，在箱体003内形成一条筛分通道，螺旋筛分管道004设计趋斜角度为45度到80度，并且进出口的距离垂直投影在平面上的直线长度大于等于三个燃料球002的直径；螺旋筛分轨道004圆环的平面投影直径小于燃料球直径5mm，通道任两环间的直线距离为燃料球直径的85％，保证较大的碎片能通过。箱体003设计承压能力大于9MPa，并在箱体上设有检查孔022，以便检修期间对箱内情况进行检查。
在装置投运时，燃料球002与其碎片以及在堆芯内流动磨损产生的石墨粉尘020一同由燃料球进口001进入螺旋筛分轨道004，在螺旋筛分通道004内，燃料球002与其碎片以及在堆芯内流动磨损产生的石墨粉尘020混合特经过螺旋筛分管道004后，被分成两路，一路是未损坏的燃料球或损伤不严重且进入阻流器后不会导致其它燃料球被切的燃料球002通过，经导流喇叭口005后进入燃料球出口006，经燃料球出口006后进入阻流器。为了避免燃料球002在到达燃料球出口006后才产生碎片对阻流器正常工作的影响，在燃料球出口006处设计有电磁阻流开关007，当阻流工作异常时，电磁阻流开关工作，将燃料球002阻挡，等阻流器工作两次后电磁阻流开关停止工作再将燃料球002放行，保证阻流器运行正常。
被筛分的另一路燃料是直径小于80％的燃料球碎片及石墨粉尘020经螺旋管道004筛分后掉进021缓冲斗内，并经隔离阀008进入核燃料球碎片缓冲罐010内缓存，再由排放阀011进入废燃料排出管道013，最后排入乏燃料储存系统管道。
在缓冲斗021下部设计有隔离阀008，隔离阀008上与缓冲斗021相连，下与核燃料球碎片缓冲罐010相连。隔离阀008打开后，被分离下的燃料球碎片及石墨粉尘020能够掉进缓冲斗021内暂存。
设计隔离门008由上下两块圆形的钢板组成，每块钢板中间分别开有一 个“8”字形孔，如图2所示，处于上部的钢板边缘设有驱动齿轮，在需要关闭或打开的情况下由气动或电动驱动装置009驱动，上部的钢板能够在90度的范围内正反两个方向转动，当两块钢板之间两孔有重叠时通道打开，核废料以及石墨粉尘可以从缓冲斗021直接进入核燃料球碎片缓冲罐010。当两块钢板之间两孔无重叠时通道关闭，核废料以及石墨粉尘禁止从缓冲斗021直接进入核燃料球碎片缓冲罐010。
核燃料球碎片缓冲罐010上部与隔离阀008相连，下部与排放阀011相连，为了在正常运行中能够检测到核燃料球碎片缓冲罐010的料位，在核燃料球碎片缓冲罐010上端设计有料位测量元件019，当料位升高时，料位测量元件019达到一定高度时，系统执行排料程序，将核燃料球碎片缓冲罐010内部的碎片以及石墨粉尘020排至废料排出管道013。
在核燃料球碎片缓冲罐010下设计有排放阀011，上部与核燃料球碎片缓冲罐010相连，下部与乏燃料排放管道相连，其结构与隔离阀008相同，由上下两块圆形的钢板组成，每块钢板中间分别开有一个“8”字形孔，如图2所示，处于上部的钢板边缘设有驱动齿轮，在需要关闭或打开的情况下由009气动或电动驱动装驱动，上部的钢板能够在90度的范围内正反两个方向转动，当两块钢板之间两孔有重叠时通道打开，核废料以及石墨粉尘可以从核燃料球碎片缓冲罐010直接进入废料排出管道013。当两块钢板之间两孔无重叠时通道关闭，核废料以及石墨粉尘禁止从核燃料球碎片缓冲罐010进入废料排出管道013。
在正常运行工况下，筛分装置003内部一直存在大于7-9MPa的压力，为避免事故发生，核燃料球碎片缓冲罐010的进料控制阀和排料控制必须按照程序执行，即当隔离阀008打开排料至核燃料球碎片缓冲罐010前，必须将排放阀011关闭，将核燃料球碎片缓冲罐010与废料排放管道013间的第二阀门017关闭，将核燃料球碎片缓冲罐010与燃料球出口管道006间的第一阀门015关闭，将核燃料球碎片缓冲罐010抽真空阀023关闭，打开第一阀门015，压力测量元件024的压力上升与系统压力平衡时打开隔离阀008。在正常运行的工况下，隔离阀008保持开状态。当料位信号019发出时，隔离阀008关闭，进行排料程序。
当核燃料球碎片缓冲罐010进料结束后，系统则执行排料程序，即关闭隔离阀008，将核燃料球碎片缓冲罐010与废料排放管道013间的第二阀门 017关闭，将核燃料球碎片缓冲罐010与燃料球出口管道006间的第一阀门015关闭，将核燃料球碎片缓冲罐010抽真空阀023打开，压力测量元件024的压力下降与废料排放管道013的压力平衡时，关闭抽真空阀23，打开隔离阀011，将碎片以及石墨粉尘020排放至乏燃料排放管道013，再输送到乏燃料储存罐。
为保证在抽真空阀023故障的情况下进排料，当抽真空阀故障无法抽吸时，打开隔离阀008进料前，将排放阀011关闭，将核燃料球碎片缓冲罐010与废料排放管道013间的第二阀门017关闭，将核燃料球碎片缓冲罐010与燃料球出口管道006间的第一阀门015关闭，将核燃料球碎片缓冲罐010抽真空阀023关闭，打开第一阀门015，压力测量元件024的压力上升与系统压力平衡时打开隔离阀008，碎片以及石墨粉尘020排放至核燃料球碎片缓冲罐010。
同样地，当抽真空阀023无法抽吸且核燃料球碎片缓冲罐010需排料时，则关闭隔离阀008，将核燃料球碎片缓冲罐010与废料排放管道013间的第二阀门017关闭，将核燃料球碎片缓冲罐010与燃料球出口管道006间的第一阀门015关闭，将核燃料球碎片缓冲罐010抽真空阀023关闭，打开第二阀门017，压力测量元件024的压力下降与废料排放管道013的压力平衡时，打开隔离阀011，将碎片以及石墨粉尘020排放至乏燃料排放管道013，再输送到乏燃料储存罐。
最后应说明的是：以上各实施例仅用以说明本申请的技术方案，而非对其限制；尽管参照前述各实施例对本申请进行了详细的说明，本领域的普通技术人员应当理解：其依然可以对前述各实施例所记载的技术方案进行修改，或者对其中部分或者全部技术特征进行等同替换；而这些修改或者替换，并不使相应技术方案的本质脱离本申请各实施例技术方案的范围。

Claims (10)

  1. 一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置，其特征在于，包括箱体(003)、螺旋筛分轨道(004)、燃料球进口(001)、燃料球出口(006)和废料出口(013)；箱体(003)设置在阻流器进口管道上，箱体(003)的顶部设置有燃料球进口(001)，底部设置有燃料球出口(006)和废料出口(013)；在箱体(003)的内部，燃料球进口(001)和燃料球出口(006)之间设置有螺旋筛分轨道(004)，且螺旋筛分轨道(004)有一定的角度，为倾斜状态，废料出口(013)位于螺旋筛分轨道(004)的下方。
  2. 根据权利要求1所述的一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置，其特征在于，螺旋筛分轨道(004)的倾斜角度为45°到80°，并且螺旋筛分轨道(004)进出口的距离垂直投影在平面上的直线距离大于等于三个燃料球的直径；螺旋筛分轨道(004)圆环的平面投影直径小于燃料球直径5mm，螺旋筛分轨道(004)任两环间的直线距离为燃料球直径的85％。
  3. 根据权利要求1所述的一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置，其特征在于，螺旋筛分轨道(004)上设置均匀的螺旋筛分间隔，筛分间隔用于筛分直径小于80％的燃料球与石墨粉尘。
  4. 根据权利要求1所述的一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置，其特征在于，燃料球出口(006)的顶部设置有导流喇叭口(005)，螺旋筛分管道(004)的出口连接导流喇叭口(005)。
  5. 根据权利要求4所述的一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置，其特征在于，螺旋轨道燃料球出口(006)上还设置有电磁阻流开关(007)。
  6. 根据权利要求1所述的一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置，其特征在于，废料出口(013)的上方设置有缓冲斗(021)和核燃料球碎片缓冲罐(010)；缓冲斗(021)连接在核燃料球碎片缓冲罐(010)的顶部，废料出口(013)连接在核燃料球碎片缓冲罐(010)的底部。
  7. 根据权利要求6所述的一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置，其特征在于，缓冲斗(021)和核燃料球碎片缓冲罐(010)的连接处设置有隔离阀(008)，隔离阀(008)由上下两块圆形的钢板组成，钢板中间分别开有一个“8”字形孔；钢板连接有驱动装置，当两块钢板之间两孔有重叠时通道打开，交错时密封关闭。
  8. 根据权利要求7所述的一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置，其特征在于，废料出口(013)和核燃料球碎片缓冲罐(010)的连接处设置有排放阀(011)，排放阀(011)的结构和隔离阀(008)结构相同。
  9. 根据权利要求8所述的一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置，其特征在于，核燃料球碎片缓冲罐(010)上设置有料位测量元件(19)、压力测量元件(024)和连通管路，连通管路上设置有抽真空阀(023)；废料出口(013)和燃料球出口(006)之间设置有抽真空联通管路，在联通管路上分别设置有手动隔离阀门(014)和(015)和气动隔离阀门(017)和(018)。
  10. 根据权利要求(1)所述的一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置，其特征在于，箱体(003)上设置有检查孔(022)。
PCT/CN2023/090143 2023-02-21 2023-04-23 一种高温气冷堆核电燃料装卸系统燃料元件碎片筛分装置 Ceased WO2024174372A1 (zh)

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