WO2020006975A1 - 核电站主泵应急注入水系统过滤装置 - Google Patents

核电站主泵应急注入水系统过滤装置 Download PDF

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Publication number
WO2020006975A1
WO2020006975A1 PCT/CN2018/118807 CN2018118807W WO2020006975A1 WO 2020006975 A1 WO2020006975 A1 WO 2020006975A1 CN 2018118807 W CN2018118807 W CN 2018118807W WO 2020006975 A1 WO2020006975 A1 WO 2020006975A1
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Prior art keywords
cavity
main pump
nuclear power
filtering device
injection water
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PCT/CN2018/118807
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English (en)
French (fr)
Inventor
陈兴江
李中双
张翊勋
宋小伍
Original Assignee
中广核工程有限公司
沈阳鼓风机集团核电泵业有限公司
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Priority to EP18925074.9A priority Critical patent/EP3819015A4/en
Publication of WO2020006975A1 publication Critical patent/WO2020006975A1/zh

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    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D36/00—Filter circuits or combinations of filters with other separating devices
    • B01D36/04—Combinations of filters with settling tanks
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D29/00—Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups B01D24/00 - B01D27/00; Filtering elements therefor
    • B01D29/01—Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups B01D24/00 - B01D27/00; Filtering elements therefor with flat filtering elements
    • B01D29/03—Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups B01D24/00 - B01D27/00; Filtering elements therefor with flat filtering elements self-supporting
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B01—PHYSICAL OR CHEMICAL PROCESSES OR APPARATUS IN GENERAL
    • B01D—SEPARATION
    • B01D36/00—Filter circuits or combinations of filters with other separating devices
    • B01D36/04—Combinations of filters with settling tanks
    • B01D36/045—Combination of filters with centrifugal separation devices
    • 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
    • G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
    • 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
    • G21C15/243—Promoting flow of the coolant for liquids
    • 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 invention belongs to the field of filtering devices, and more particularly, the invention relates to a filtering device for an emergency injection water system of a main pump of a nuclear power plant.
  • the main pump is one of the key equipment of the primary circuit system of the PWR nuclear power plant.
  • the reliable operation of the main pump plays a vital role in the continuous and safe operation of the nuclear power plant.
  • a water lubricated bearing and a shaft seal assembly are provided on the pump body.
  • a shaft seal injection water system is provided on the pump body.
  • the shaft seal injection water is provided by the top-up water from the chemical and volume control (RCV) system.
  • RCV chemical and volume control
  • an emergency shaft seal injection water system is usually provided.
  • the emergency shaft seal injection water system takes water from the main pump casing and cools it into the shaft seal cavity after being cooled by an external heat exchanger to provide lubrication and cooling for the shaft seal assembly and water-lubricated bearings.
  • the medium for the emergency shaft seal injection water system is derived from the coolant of the primary loop reactor, which needs to be filtered before being injected into the shaft seal chamber.
  • the existing main pump emergency shaft seal injection water filtration device adopts the hydrocyclone separation technology, and is composed of a container, a conical tube, an overflow tube, a cover plate and a sealing ring.
  • the container is provided with an inlet, an outlet and a sewage outlet.
  • the inlet and the outlet are respectively welded and connected to the inlet and outlet pipes.
  • the sewage outlet is connected to the sewage pipeline through a flange.
  • An isolation valve is provided on the sewage pipeline.
  • the cover is connected to the container by bolts.
  • the upper part of the container, the overflow pipe and the conical tube constitute a hydrocyclone.
  • Emergency injection water enters from the inlet along the tangential direction of the conical tube, and a swirling motion is formed in the conical tube.
  • the part of the liquid containing fine particles flows out through the overflow pipe above the conical tube, enters the upper cavity of the overflow pipe, and flows out along the horizontal discharge port in the cavity.
  • a part of the liquid is discharged from the lower end of the conical tube into the container cavity. Solid particles and impurities are deposited in the container, and the isolation in the container is regularly removed and cleaned by opening the isolation valve on the sewage line.
  • This kind of main pump emergency shaft seal injection water filtering device has certain defects: 1) because the sewage outlet below the container is closed, the medium in the container is stationary, and the effect of hydrocyclone separation is weakened; 2) in the initial stage, the hydrocyclone The separation accuracy and efficiency are high, but with the use of time, the concentration of solid particles and impurities in the container is getting higher and higher, and the swirling flow creates a mixing effect in the container, and the solid cannot be deposited on the bottom of the container; 3) hydrocyclone separator Can not play the role of hydrocyclone separation, thereby greatly reducing the accuracy and efficiency of hydrocyclone separation, can not achieve the role of filtration.
  • the purpose of the invention is to overcome the shortcomings of the prior art and provide a filter device for an emergency injection water system of a main pump of a nuclear power plant with a compact structure, safety and reliability, high separation accuracy and separation efficiency, and good sedimentation performance.
  • the present invention provides a filtering device for an emergency injection water system of a main pump of a nuclear power plant, which is characterized by including:
  • the pressure-bearing component includes a cavity, an upper head, a cylinder and a lower head which are fixedly connected in order from top to bottom, and the cavity has a water inlet, a water outlet and an overflow port;
  • the cover plate is fixedly connected to the top of the cavity, and a cavity is formed between the cover plate and the cavity;
  • a seal ring is arranged between the cover plate and the cavity
  • the sedimentation and separation component is installed in the cylinder.
  • the settlement and separation component includes an umbrella-shaped pollution blocking plate, a conical deflector and a filter screen, the umbrella-shaped pollution blocking plate and a conical deflector Alternately arranged from top to bottom, the number of umbrella-shaped pollution-retaining plates is at least one more than the number of conical deflectors, and a filter is arranged below the umbrella-shaped pollution-retaining plate at the bottom.
  • the cone-shaped deflector is fixed on the cylinder body by welding
  • the umbrella-shaped pollution prevention board is provided with a plurality of legs
  • the lowermost umbrella The shaped pollution-retaining plate is directly welded and fixed to the cylinder body through the legs, and the other umbrella-shaped pollution-retaining plate is welded and fixed through the legs and the conical deflector.
  • the water inlet is connected with an inlet flange
  • the water outlet is connected with an outlet flange
  • the bottom of the lower head is fixedly connected with a sewage outlet flange
  • the cavity, the upper head, the cylinder, the lower head, the inlet flange, the outlet flange, and the sewage outlet flange are integrated into a whole by welding.
  • the inlet flange is connected to the matching flange of the emergency injection water pipeline
  • the outlet flange is connected to the matching flange of the water outlet pipeline
  • the sewage is discharged
  • the mouth flange is connected to the paired flange of the sewage pipe.
  • an isolation valve is provided on the sewage pipeline, and the isolation valve is in a closed state during normal operation.
  • the water inlet is of a rectangular structure, the rectangular vertical plane is tangent to the inner wall of the annular groove in the cavity, and the injected water passes through the annular groove and enters the conical tube to form Swirl movement.
  • the cover plate is connected to the cavity by bolts.
  • the lower head is tapered.
  • the filtering device of the emergency injection water system of the main pump of the nuclear power plant is made of stainless steel.
  • the filtering device of the emergency injection water system of the main pump of the nuclear power plant of the present invention has the following beneficial technical effects:
  • the pressure-bearing components of the filter device adopt an integrated structure, and the welded structure between each part ensures the integrity of the pressure boundary.
  • FIG. 1 is a schematic structural diagram of a filtering device for an emergency injection water system of a main pump of a nuclear power plant according to the present invention.
  • Fig. 2 is a schematic sectional view of a filter device cavity of a main pump emergency injection water system of a nuclear power plant according to the present invention.
  • Fig. 3 is a schematic cross-sectional view of A-A of the filtering device of the emergency injection water system of the main pump of the nuclear power plant of the present invention.
  • Fig. 4 is a B-B sectional schematic view of a filtering device for an emergency injection water system of a main pump of a nuclear power plant according to the present invention.
  • FIG. 5 is a schematic diagram of the working principle of a filtering device for an emergency injection water system of a main pump of a nuclear power plant according to the present invention.
  • the filtering device of the emergency injection water system of the main pump of the nuclear power plant of the present invention includes:
  • the pressure-bearing component includes a cavity 12, an upper head 14, a cylinder 16, and a lower head 18 which are fixedly connected in order from top to bottom.
  • the cavity 12 has a water inlet 120, a water outlet 122, and an overflow outlet 124. 120 is connected to the inlet flange 20, the water outlet 122 is connected to the outlet flange 22, and the bottom head 18 is fixedly connected to the drain flange 24 at the bottom;
  • the cover plate 26 is fixedly connected to the top of the cavity 12, and a cavity 126 is formed between the cover plate 26 and the cavity 12;
  • a seal ring 28 is disposed between the cover plate 26 and the cavity 12;
  • the sedimentation separation member 32 is provided in the cylindrical body 16.
  • the cavity 12, the upper head 14, the cylinder 16, the lower head 18, the inlet flange 20, the outlet flange 22, and the sewage outlet flange 24 are welded to form a whole, which constitutes the pressure boundary of the entire device.
  • the middle part of the cavity 12 is provided with an annular groove 121 and an overflow opening 124.
  • the water inlet 120 and the water outlet 122 on the cavity 12 are extended to both sides, and the water inlet 120 is located at After the cavity 12 is welded to the inlet flange 20 at the lower part of the water outlet 122, the water inlet 120 communicates with the through hole of the inlet flange 20. After the cavity 12 is welded to the outlet flange 22, the water outlet 122 communicates with the through hole of the outlet flange 22.
  • the water inlet 120 has a rectangular structure, and the rectangular vertical plane is tangent to the inner wall of the annular groove 121 of the cavity 12.
  • the upper head 14 has a tapered structure, the upper part is welded to the lower part of the cavity 12, the lower part is welded to the upper part of the cylinder 16, and the lower part of the upper head 14 is consistent with the inner diameter and outer diameter of the cylinder 16.
  • the cylinder 16 has a cylindrical structure, and an upper portion is welded to the lower portion of the upper head 14 and a lower portion is welded to the upper portion of the lower head 18.
  • a drain port 180 is provided at the bottom of the lower head 18 and is welded to the drain port flange 24.
  • the drain port 180 communicates with the through hole of the drain port flange 24.
  • the lower head 18 has a tapered structure, and the upper and inner diameters of the cylinder body 16 are the same.
  • the width of the lower portion is much smaller than the width of the upper portion, which facilitates the final settlement of solid particles and impurities at the lowest position.
  • the cover plate 26 is fixed to the cavity 12 by bolts, and a cavity 126 is formed between the cover plate 26 and the cavity 12.
  • a sealing ring 28 is provided before the cover plate 26 and the cavity 12 are fixedly connected. Then, the cover plate 26 and the cavity 12 are fixedly connected with bolts to facilitate washing and decontamination inside the filtering device.
  • the conical tube 30 is located in a circular cavity formed by the lower portion of the cavity 12 and the upper head 14, and the diameter and height of the circular cavity formed by the lower portion of the cavity 12 and the upper head 14 are different from the diameter and height of the conical tube 30. Consistent, the conical tube 30 is connected with the cavity 12 and the upper head 14 through an interference fit; the upper diameter of the conical tube 30 is consistent with the outer diameter of the annular groove 121 in the cavity 12, and the upper portion of the conical tube 30 and the cavity are respectively.
  • the annular groove 121 of 12 communicates with the overflow port 124, and the lower part communicates with the upper head 14; the top of the overflow port 124 communicates with the cavity 126 between the cover plate 126 and the cavity 12, and the cavity 126 communicates with the cavity 12
  • the water outlet 122 communicates. After the injected water flows from the water inlet 120, it enters the conical tube 30 through the annular groove 121 to form a swirling motion.
  • the inlet flange 20 is connected to the mating flange of the emergency injection water line (not shown), the outlet flange 22 is connected to the mating flange of the water outlet line (not shown), and the sewage outlet flange 24 is connected to the sewage line (FIG. Not shown) Mating flange connection.
  • An isolation valve (not shown) is provided on the sewage pipeline (not shown). During normal operation, the isolation valve (not shown) is in a closed state.
  • the sedimentation and separation member 32 is disposed in the cylinder body 16, and the upper part does not exceed the welding point between the cylinder body 16 and the upper head 14, and the lower part does not exceed the welding point between the cylinder body 16 and the lower head 18.
  • the settling and separating component 32 includes an umbrella-shaped dirt-retaining plate 320, a conical deflector 322, and a strainer 324.
  • the top of the umbrella-type dirt-retaining plate 320 is pointed and the bottom is horizontally arranged.
  • the width of the bottom is much larger than the width of the top.
  • the upper width of the shape deflector 322 is larger than the lower width.
  • Umbrella-shaped pollution-retaining plates 320 and conical deflectors 322 are alternately arranged from top to bottom, and the number of the umbrella-shaped pollution-retaining plates 320 is at least one more than the number of the conical deflectors 322. Both and below are provided with umbrella-shaped dirt blocking plates 320.
  • the filter screen 324 is disposed below the lowermost umbrella-shaped dirt blocking plate 320, and the filter screen 324 is disposed at a position that does not exceed the welding point of the cylinder 16 and the lower head 18.
  • the filter screen 324 may also be disposed between the umbrella-shaped pollution-retaining plate 320 and the conical deflector 322 alternately as required, and the filter screen 324 may be provided below the umbrella-type pollution-retaining plate 320. It may be disposed below the conical deflector 322.
  • the setting manners are: umbrella-shaped dirt blocking plate 320, cone-shaped deflector 322, umbrella-shaped dirt blocking plate 320, and filter screen 324;
  • the setting method is: umbrella-shaped pollution-retaining plate 320, cone-shaped deflector 322, umbrella-shaped fouling plate 320, cone-shaped deflector 322, umbrella-shaped fouling plate 320, and Strainer 324;
  • the number of the cone-shaped deflectors 322 is multiple, the umbrella-shaped pollution-retaining plates 320 and the cone-shaped pollution-receiving plates 322 are alternately arranged in order, and the umbrella-type pollution-retaining plates 320 are arranged below to end the alternation. All the cone-shaped deflectors 322 are alternately arranged between all the umbrella-shaped pollution-retaining plates 320, and a strainer 324 is arranged at the lowermost part.
  • the filter screen 324 is a round-hole screen structure, and is arranged near the cylinder 16 and the lower head 18, and the filter screen 324 is fixed to the inner wall of the cylinder 16 by welding.
  • the umbrella-shaped pollution-retaining plate 320 and the conical deflector 322 are arranged as evenly as possible inside the cylinder body 16.
  • the conical flow-guide plate 322 is fixed to the cylinder 16 by welding.
  • four legs 3200 are evenly arranged.
  • the lowermost umbrella-shaped dirt-retaining plate 320 is directly welded and fixed to the cylinder 16 through the legs 3200, and the other umbrella-shaped dirt-retaining plates 320 pass through.
  • the leg 3200 is welded and fixed to the tapered deflector 322.
  • the assembly process of the filtering device of the emergency injection water system of the main pump of the nuclear power plant of the present invention will be described with reference to FIG. 1.
  • the assembly process is as follows, wherein the order of steps 1) to 3) can be adjusted, and step 4) is finally completed:
  • Step 3) Weld the drain outlet flange 24 to the lower part of the lower head 18;
  • FIG. 1 and FIG. 5 Please refer to FIG. 1 and FIG. 5 to describe the working principle of the emergency injection water filtration device of the main pump of the nuclear power plant of the present invention:
  • the inlet 120 and outlet 122 of the emergency injection water filtering device of the main pump of the nuclear power plant are horizontally arranged, and the overflow opening 124 is provided in the center of the cavity 12, and an annular groove 121 is provided in the middle of the cavity.
  • the outer diameter of the annular groove 121 and the conical tube The inner diameter of 30 upper holes is the same.
  • Part of the liquid containing traces of fine particles flows vertically upward through the overflow opening 124 in the cavity 12, enters the cavity 126 between the cavity 12 and the cover plate 26, and flows out horizontally from the outlet flange 22 to be injected into the shaft seal
  • the chamber (not shown) provides the shaft seal injection water for the main pump shaft seal assembly. Under the action of centrifugal force, the larger particles settle to the inner wall surface of the tapered tube 30 while being driven by the pressure difference, and the other part of the liquid is discharged from the lower end of the tapered tube 30 and enters the upper head 14 below.
  • the cylinder 16 and the lower head 18 are welded and connected in a container.
  • the sedimentation and separation module changes the flow direction of solid particles and impurities on the one hand, and prevents the media from mixing, preventing the solid particles and impurities from flowing upward, improving and improving the sedimentation separation performance, thereby improving the separation of the emergency injection water filtration device of the main pump of the entire nuclear power plant. Precision and separation efficiency.
  • the isolation valve (not shown) on the sewage pipeline (not shown) is closed, and solid particles and impurities are removed and cleaned during the nuclear power plant shutdown and refueling maintenance.
  • the filtering device of the emergency injection water system of the main pump of the nuclear power plant of the present invention has the following beneficial technical effects:
  • the sedimentation and separation component 32 is provided to realize the collection and deposition of solid particles and impurities. When the sewage outlet is closed, the separation and sedimentation effect is improved, and the decontamination and cleaning cycle of the filter device is extended;
  • the pressure-bearing components of the filter device adopt an integrated structure, and the welded structure between each part ensures the integrity of the pressure boundary.

Abstract

一种核电站主泵应急注入水系统过滤装置，包括：承压部件，包括从上至下依次固定连接的腔体（12）、上封头（14）、筒体（16）和下封头（18），腔体（12）具有进水口（120）、出水口（122）和溢流口（124）；盖板（26）与腔体（12）顶部固定连接，并与腔体（12）之间形成有空腔（126）；密封圈（28）设置于盖板（26）和腔体（12）之间；锥形管（30）嵌入于腔体（12）和上封头（14）内；以及沉降分离部件（32）设置于筒体（16）内。

Description

核电站主泵应急注入水系统过滤装置 技术领域
本发明属于过滤装置领域，更具体地说，本发明涉及一种核电站主泵应急注入水系统过滤装置。
背景技术
主泵是压水堆核电站一回路系统的关键设备之一，主泵的可靠运转对核电站连续安全运行起着至关重要的作用。对于轴封型主泵，在泵本体上设置有水润滑轴承和轴封组件。为保证轴封组件和水润滑径向轴承的冷却和润滑，防止高温、高压冷却剂向叶轮上方的轴系传导，使水润滑径向轴承和轴封组件在可接受的温度范围内运行，需要在泵本体上设置轴封注入水系统，正常情况下轴封注入水由来自化学和容积控制(RCV)系统的上充水提供。为确保在RCV轴封注入水失效的情况下主泵可以正常运行，通常设置有应急轴封注入水系统。应急轴封注入水系统从主泵泵壳内取水，经过外部热交换器冷却后注入轴封腔，为轴封组件和水润滑轴承提供润滑和冷却。而应急轴封注入水系统的介质来源于一回路反应堆冷却剂，需要对其进行过滤后才能将其注入到轴封腔室。
现有主泵应急轴封注入水过滤装置采用旋液分离技术，由容器、锥形管、溢流管、盖板和密封圈组成。容器上设置有入口、出口和排污口，入口和出口分别与进出口管道焊接连接，排污口通过法兰与排污管线连接，排污管线上设置有隔离阀。盖板通过螺栓与容器连接在一起。容器上部及溢流管和锥形管构成旋液分离器，应急注入水从入口沿锥形管的切线方向进入，在锥形管内形成旋流运动。含细小颗粒的那部分液体通过锥形管上方的溢流管流出，进入溢流管上部空腔，沿空腔内的水平排出口流出。在离心力作用下，较大颗粒在向锥形管内壁面沉降的同时，由于有压力差的推动力作用，则随一部分液体从锥形 管下端排出进入容器空腔内。固体颗粒和杂质在容器内沉积，定期通过打开排污管线上的隔离阀对容器内的沉积物进行排除和清洗。
这种主泵应急轴封注入水过滤装置具有一定缺陷：1)由于容器下方的排污口处于关闭状态，容器内的介质处于静止状态，旋液分离的效果减弱；2)在初始阶段，旋液分离精度和效率较高，但随着使用时间的延长，容器内固体颗粒和杂质的浓度越来越高，旋流在容器内产生搅混作用，固体无法在容器底部沉积；3)旋液分离器不能起到旋液分离的作用，从而大大降低了旋液分离精度和效率，不能实现过滤的作用。
有鉴于此，确有必要提供一种结构紧凑、安全可靠、分离精度和分离效率高、沉降性能好的核电站主泵应急注入水系统过滤装置。
发明内容
本发明的发明目的在于：克服现有技术的不足，提供一种结构紧凑、安全可靠、分离精度和分离效率高、沉降性能好的核电站主泵应急注入水系统过滤装置。
为了实现上述发明目的，本发明提供了一种核电站主泵应急注入水系统过滤装置，其特征在于，包括：
承压部件，包括从上至下依次固定连接的腔体、上封头、筒体和下封头，腔体具有进水口、出水口和溢流口；
盖板，与腔体顶部固定连接，并与腔体之间形成有空腔；
密封圈，设置于盖板和腔体之间；
锥形管，嵌入于腔体和上封头内；以及
沉降分离部件，设置于筒体内。
作为本发明核电站主泵应急注入水系统过滤装置的一种改进所述沉降分离部件包括伞形拦污板、锥形导流板和滤网，所述伞形拦污板和锥形导流板从上至下交替设置，伞形拦污板的数量比锥形导流板的数量至少多一个，且最下方的伞形拦污板的下方设置有滤网。
作为本发明核电站主泵应急注入水系统过滤装置的一种改进，所述锥形导 流板通过焊接固定在筒体上，所述伞形拦污板设置有多个支腿，最下方的伞形拦污板通过支腿直接与筒体焊接固定，其余伞形拦污板通过支腿与锥形导流板焊接固定。
作为本发明核电站主泵应急注入水系统过滤装置的一种改进，所述进水口连接有入口法兰，出水口连接有出口法兰，下封头底部固定连接有排污口法兰。
作为本发明核电站主泵应急注入水系统过滤装置的一种改进，所述腔体、上封头、筒体、下封头、入口法兰、出口法兰、排污口法兰通过焊接组成一个整体。
作为本发明核电站主泵应急注入水系统过滤装置的一种改进，所述入口法兰与应急注入水管线的配对法兰连接，所述出口法兰与出水管线的配对法兰连接，所述排污口法兰与排污管线配对法兰连接。
作为本发明核电站主泵应急注入水系统过滤装置的一种改进，所述排污管线上设置有隔离阀，正常运行期间，隔离阀处于关闭状态。
作为本发明核电站主泵应急注入水系统过滤装置的一种改进，所述进水口为矩形结构，矩形的垂直面与腔体内的环形槽内壁相切，注入水经过环形槽后进入锥形管内形成旋流运动。
作为本发明核电站主泵应急注入水系统过滤装置的一种改进，所述盖板通过螺栓与腔体连接。
作为本发明核电站主泵应急注入水系统过滤装置的一种改进，所述下封头为锥形。
作为本发明核电站主泵应急注入水系统过滤装置的一种改进，所述核电站主泵应急注入水系统过滤装置采用不锈钢材料制成。
相对于现有技术，本发明核电站主泵应急注入水系统过滤装置具有以下有益技术效果：
1)提高了过滤精度和过滤效率；
2)结构紧凑，零部件数量少；
3)通过设置沉降分离部件，可以实现固体颗粒和杂质的收集与沉积，在排 污口封闭的情况下，提高了分离和沉降效果，延长了过滤装置的去污和清洗周期；
4)过滤装置的承压部件采用一体化结构，各部分之间采用焊接结构，确保了压力边界的完整性。
附图说明
下面结合附图和具体实施方式，对本发明核电站主泵应急注入水系统过滤装置进行详细说明，其中：
图1为本发明核电站主泵应急注入水系统过滤装置的结构示意图。
图2为本发明核电站主泵应急注入水系统过滤装置腔体的剖视示意图。
图3为本发明核电站主泵应急注入水系统过滤装置的A-A剖视示意图。
图4为本发明核电站主泵应急注入水系统过滤装置的B-B剖视示意图。
图5为本发明核电站主泵应急注入水系统过滤装置的工作原理示意图。
附图标记：
12-腔体；120-进水口；121-环形槽；122-出水口；124-溢流口；126-空腔；14-上封头；16-筒体；18-下封头；180-排污口；20-入口法兰；22-出口法兰；24-排污口法兰；26-盖板；28-密封圈；30-锥形管；32-沉降分离部件；320-伞形拦污板；322-锥形导流板；324-滤网。
具体实施方式
为了使本发明的发明目的、技术方案及其技术效果更加清晰，以下结合附图和具体实施方式，对本发明进行进一步详细说明。应当理解的是，本说明书中描述的具体实施方式仅仅是为了解释本发明，并非为了限定本发明。
请参阅图1至图5所示，本发明核电站主泵应急注入水系统过滤装置包括：
承压部件，包括从上至下依次固定连接的腔体12、上封头14、筒体16和下封头18，腔体12具有进水口120、出水口122和溢流口124，进水口120连 接有入口法兰20，出水口122连接有出口法兰22，下封头18底部固定连接有排污口法兰24；
盖板26，与腔体12顶部固定连接，并与腔体12之间形成有空腔126；
密封圈28，设置于盖板26和腔体12之间；
锥形管30，嵌入于腔体12和上封头14内；以及
沉降分离部件32，设置于筒体16内。
腔体12、上封头14、筒体16、下封头18、入口法兰20、出口法兰22、排污口法兰24通过焊接组成一个整体，构成整个装个装置的压力边界。
请参阅图1和图2所示，腔体12的中部设置有一个环形槽121和溢流口124，腔体12上的进水口120和出水口122朝两侧延伸设置，且进水口120位于出水口122的下部，腔体12与入口法兰20焊接连接后，进水口120与入口法兰20的通孔连通。腔体12与出口法兰22焊接连接后，出水口122与出口法兰22的通孔连通。进水口120为矩形结构，矩形的垂直面与腔体12的环形槽121内壁相切。
上封头14为锥形结构，上部与腔体12的下部焊接连接，下部与筒体16的上部焊接连接，上封头14的下部与筒体16的内径和外径一致。
筒体16为圆柱形结构，上部与上封头14下部焊接连接，下部与下封头18上部焊接连接。
下封头18的底部设置有排污口180，并与排污口法兰24焊接连接，排污口180与排污口法兰24的通孔连通。下封头18为锥形结构，上部与筒体16的内径和外径一致，下部的宽度远小于上部的宽度，便于固体颗粒和杂质最终沉降在最低位置。
盖板26通过螺栓固定在腔体12上，且盖板26与腔体12之间形成有空腔126，为了保证气密性，在盖板26与腔体12固定连接之前设置密封圈28，然后再用螺栓将盖板26和腔体12进行固定连接，便于过滤装置内部的冲洗和去污。
锥形管30位于腔体12下部和上封头14上部构成的圆形空腔内，腔体12下部和上封头14构成的圆形空腔直径和高度与锥形管30的直径和高度一致，锥形管30与腔体12和上封头14通过过盈配合连接；锥形管30上部孔径与腔体12内的环形槽121外径一致，锥形管30孔道上部分别与腔体12的环形槽121和溢流口124连通，下部与上封头14连通；溢流口124的顶部与盖板126和腔体12之间的空腔126连通，空腔126与腔体12的出水口122连通。注入水从进水口120流入后，经过环形槽121进入锥形管30内形成旋流运动。
入口法兰20与应急注入水管线(图未示出)的配对法兰连接，出口法兰22与出水管线(图未示出)的配对法兰连接，排污口法兰24与排污管线(图未示出)配对法兰连接。排污管线(图未示出)上设置有隔离阀(图未示出)，正常运行期间，隔离阀(图未示出)处于关闭状态。
请参阅1、图3和图4所示，沉降分离部件32设置在筒体16内，上部不超过筒体16与上封头14的焊接点，下部不超过筒体16与下封头18的焊接点。沉降分离部件32包括伞形拦污板320、锥形导流板322和滤网324，伞形拦污板320的顶部为尖形，底部水平设置，且底部的宽度远大于顶部的宽度，锥形导流板322上部宽度大于下部宽度。伞形拦污板320和锥形导流板322从上至下交替设置，且伞形拦污板320的数量比锥形导流板322的数量至少多一个，锥形导流板322的上方和下方都设置有伞形拦污板320。滤网324设置在最下方的伞形拦污板320的下方，且滤网324设置位置不会超过筒体16与下封头18的焊接点。在其他实施方式中，滤网324也可根据需要设置在交替设置的伞形拦污板320和锥形导流板322之间，滤网324可设置在伞形拦污板320的下方，也可设置在锥形导流板322的下方。
具体地，当只设置有一个锥形导流板322时，设置方式依次为：伞形拦污板320、锥形导流板322、伞形拦污板320和滤网324；当锥形导流板322的数量为两个时，设置方式依次为：伞形拦污板320、锥形导流板322、伞形拦污板320、锥形导流板322、伞形拦污板320和滤网324；当锥形导流板322的数量为多个时，伞形拦污板320和锥形导流板322依次交替设置，并在下方以设置 伞形拦污板320结束交替，将所有锥形导流板322交替设置在所有伞形拦污板320之间，同时在最下部设置滤网324。
滤网324为圆孔筛结构，设置在靠近筒体16和下封头18的位置，且滤网324与筒体16内壁焊接固定。
优选地，伞形拦污板320和锥形导流板322尽量均匀设置在筒体16内部，锥形导流板322通过焊接方式固定在筒体16上，伞形拦污板320设置有多个支腿3200，在图示实施方式中，均匀设置有4个支腿3200，最下方的伞形拦污板320通过支腿3200直接与筒体16焊接固定，其余伞形拦污板320通过支腿3200与锥形导流板322焊接固定。
结合图1对本发明核电站主泵应急注入水系统过滤装置的装配过程进行说明，其装配过程如下，其中步骤1)～3)的顺序可以调整，步骤4)最后完成：
步骤1)：将沉降分离部件32的伞形拦污板320、锥形导流板322和过滤网固定在筒体16内；
步骤2)：将锥形管30装入上封头14，并装上腔体12，然后将上封头14上部与腔体12下部焊接，再将入口法兰20和出口法兰22与腔体12焊接；
步骤3)：在下封头18下部焊接排污口法兰24；
步骤4)：在筒体16上部焊接上封头14，在下部焊接下封头18。
请参阅图1和图5所示，对本发明核电站主泵应急注入水过滤装置的工作原理进行介绍：
核电站主泵应急注入水过滤装置的进水口120和出水口122水平布置，溢流口124设置在腔体12的中心，腔体中部设置有环形槽121，环形槽121的外径与锥形管30上孔内径一致。应急轴封注入水从过滤装置入口法兰20流进后，从入口沿腔体12内的环形槽121内壁的切线方向进入，在重力和压力的作用下进入锥形管30内形成旋流运动。含微量细小颗粒的一部分液体通过腔体12内的溢流口124垂直向上流动，进入腔体12和盖板26之间的空腔126内，并从出口法兰22处水平流出，注入轴封腔室(图未示出)内为主泵轴封组件提供轴封注入水。在离心力作用下，较大的颗粒在向锥形管30内壁面沉降的同时，受到 压力差的推动力作用，随另一部分液体从锥形管30下端排出，进入下方的由上封头14、筒体16和下封头18焊接连接形成的容器内。含固体颗粒和杂质的液体进入容器后，在伞形拦污板320作用下向容器四周沉降，随后进入锥形导流板322向容器中心流动，经过伞形拦污板320和锥形导流板322的多次改变流动方向后，最终通过滤网324流向容器的下封头18部位。由于下封头18为锥形结构，固体颗粒和杂质最终沉降在最低位置。沉降分离组件一方面改变固体颗粒和杂质的流动方向，另一方面，防止介质搅混，阻止固体颗粒和杂质向上流动，改善和提高沉降分离性能，从而提高整个核电站主泵应急注入水过滤装置的分离精度和分离效率。正常运行期间，排污管线(图未示出)上的隔离阀(图未示出)处于关闭状态，在核电站停堆换料检修期间，进行固体颗粒和杂质的去除与清洗。
需要说明的是，核电站主泵应急注入水系统过滤装置的所有部件都采用不锈钢材料制成。
结合以上对本发明核电站主泵应急注入水系统过滤装置的描述可知，相对于现有技术，本发明核电站主泵应急注入水系统过滤装置具有以下有益技术效果：
1)提高了过滤精度和过滤效率；
2)结构紧凑，零部件数量少；
3)通过设置沉降分离部件32，可以实现固体颗粒和杂质的收集与沉积，在排污口封闭的情况下，提高了分离和沉降效果，延长了过滤装置的去污和清洗周期；
4)过滤装置的承压部件采用一体化结构，各部分之间采用焊接结构，确保了压力边界的完整性。
根据上述原理，本发明还可以对上述实施方式进行适当的变更和修改。因此，本发明并不局限于上面揭示和描述的具体实施方式，对本发明的一些修改和变更也应当落入本发明的权利要求的保护范围内。此外，尽管本说明书中使 用了一些特定的术语，但这些术语只是为了方便说明，并不对本发明构成任何限制。

Claims (10)

  1. 一种核电站主泵应急注入水系统过滤装置，其特征在于，包括：
    承压部件，包括从上至下依次固定连接的腔体、上封头、筒体和下封头，腔体具有进水口、出水口和溢流口；
    盖板，与腔体顶部固定连接，并与腔体之间形成有空腔；
    密封圈，设置于盖板和腔体之间；
    锥形管，嵌入于腔体和上封头内；以及
    沉降分离部件，设置于筒体内。
  2. 根据权利要求1所述的核电站主泵应急注入水系统过滤装置，其特征在于，所述沉降分离部件包括伞形拦污板、锥形导流板和滤网，所述伞形拦污板和锥形导流板从上至下交替设置，伞形拦污板的数量比锥形导流板的数量至少多一个，且最下方的伞形拦污板的下方设置有滤网。
  3. 根据权利要求2所述的核电站主泵应急注入水系统过滤装置，其特征在于，所述锥形导流板通过焊接固定在筒体上，所述伞形拦污板设置有多个支腿，最下方的伞形拦污板通过支腿直接与筒体焊接固定，其余伞形拦污板通过支腿与锥形导流板焊接固定。
  4. 根据权利要求1所述的核电站主泵应急注入水系统过滤装置，其特征在于，所述进水口连接有入口法兰，出水口连接有出口法兰，下封头底部固定连接有排污口法兰。
  5. 根据权利要求4所述的核电站主泵应急注入水系统过滤装置，其特征在于，所述腔体、上封头、筒体、下封头、入口法兰、出口法兰、排污口法兰通过焊接组成一个整体。
  6. 根据权利要求5所述的核电站主泵应急注入水系统过滤装置，其特征在于，所述入口法兰与应急注入水管线的配对法兰连接，所述出口法兰与出水管线的配对法兰连接，所述排污口法兰与排污管线配对法兰连接。
  7. 根据权利要求6所述的核电站主泵应急注入水系统过滤装置，其特征在 于，所述排污管线上设置有隔离阀，正常运行期间，隔离阀处于关闭状态。
  8. 根据权利要求1所述的核电站主泵应急注入水系统过滤装置，其特征在于，所述进水口为矩形结构，矩形的垂直面与腔体内的环形槽内壁相切，注入水经过环形槽后进入锥形管内形成旋流运动。
  9. 根据权利要求1所述的核电站主泵应急注入水系统过滤装置，其特征在于，所述盖板通过螺栓与腔体连接。
  10. 根据权利要求1所述的核电站主泵应急注入水系统过滤装置，其特征在于，所述下封头为锥形。
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