CN211585391U - Built-in reloading water tank filter screen equipment of nuclear power station - Google Patents

Built-in reloading water tank filter screen equipment of nuclear power station Download PDF

Info

Publication number
CN211585391U
CN211585391U CN201921796569.8U CN201921796569U CN211585391U CN 211585391 U CN211585391 U CN 211585391U CN 201921796569 U CN201921796569 U CN 201921796569U CN 211585391 U CN211585391 U CN 211585391U
Authority
CN
China
Prior art keywords
water tank
built
refueling water
nuclear power
filter screen
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
CN201921796569.8U
Other languages
Chinese (zh)
Inventor
王涛
荚川
李勇
郑华
赵海江
王琰
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Nuclear Power Institute of China
Original Assignee
Nuclear Power Institute of China
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Nuclear Power Institute of China filed Critical Nuclear Power Institute of China
Priority to CN201921796569.8U priority Critical patent/CN211585391U/en
Application granted granted Critical
Publication of CN211585391U publication Critical patent/CN211585391U/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Images

Abstract

The utility model discloses a built-in refueling water tank filter screen device for a nuclear power station, which comprises a plurality of filter components, a confluence groove and a pipeline header; the confluence groove is used as a rigid structural support of the filter screen equipment and is fixedly arranged above a water taking pit in the built-in refueling water tank through welding connection with a built-in base in the built-in refueling water tank by adopting a frame type design; the plurality of filtering components are used as independent filtering units and are connected with the confluence groove through fasteners, and a pipeline header is arranged on one side of the confluence groove and is used for connecting a process pipeline; the coolant in the built-in refueling water tank flows into a water taking pit and a process pipeline in the built-in refueling water tank through the confluence groove after being filtered by the filtering component, so that the effect of intercepting and retaining impurities carried in the coolant and preventing the coolant from entering the water taking pit and the process pipeline is achieved.

Description

Built-in reloading water tank filter screen equipment of nuclear power station
Technical Field
The utility model relates to a fluid medium filter equipment field specifically relates to a built-in reloading water tank filter screen equipment of nuclear power station.
Background
These accidents in foreign nuclear power plants in the nineties of the last century led nuclear power safety authorities to challenge the rationality of existing pit filter screen designs and to pay attention to the relevant research of long-term recirculation stages under large break loss accidents of reactor water, and to develop a series of researches.
The operation events and subsequent research results of the nuclear power station show that the original method for evaluating the performance of the pit filter screen has the following defects:
1) the small-sized fragments originally thought to pass through the filter screen and not cause the filter screen to be blocked, but actually due to the existence of some fibrous substances, a finer fiber bed is formed on the surface of the pit filter screen, and the fiber bed can generate strong filtering effect on the small-sized fragments and cause the small-sized fragments to be accumulated on the filter screen, thereby having serious influence on the performance of the pit filter screen;
2) fine fragments passing through a pit filter screen enter a reactor core along with a reactor emergency cooling system and are possibly deposited at a fuel assembly inlet or a positioning grid, so that the flow of a coolant of the reactor core is blocked, the safety export of the residual heat of the reactor core is influenced, and the safety of a nuclear power station is seriously influenced;
3) the number of fragments generated by the breakage of the high-energy pipeline is more than that expected originally, the fragments are finer (so that the fragments are easier to migrate), and compared with the same number of single-kind fragments, the combination of different-kind fragments (such as fibrous substances and granular substances) can cause larger head loss, so that the effective cavitation allowance of the safety injection pump and the safety spray pump is influenced;
4) chemical reactions may also produce debris, which is small and sometimes fibrous, and deposits from chemical reactions may form secondary deposits on the pit screen or fiber bed of the fuel assembly, further degrading the drag characteristics of the pit screen or fuel assembly.
Aiming at the above recognition updating, a series of slag blockage experimental researches of the filter screen are developed internationally and domestically to verify the performance of the containment sump filter screen under the condition of slag blockage. Experimental research shows that the pressure loss performance of the nuclear power station can meet the requirement of functional integrity of a specially designed safety system according to a filter screen with a larger filter area. Therefore, the filter screen equipment designed based on the 50% blockage rate is not applicable, and the filter screen equipment with the built-in refueling water tank, which can fully meet the requirements of management guidance RG1.82, needs to be designed and developed.
SUMMERY OF THE UTILITY MODEL
The utility model aims at designing and developing a built-in reloading water tank filter screen equipment of nuclear power station, can be satisfying under the prerequisite that interior replacement material water tank interior installation space required, impurity in the built-in reloading water tank after filtering and intercepting nuclear power station LOCA accident reaches the purpose at clean nuclear power station LOCA accident back long-term cooling recirculation stage cooling water source.
In order to achieve the purpose, the utility model discloses a built-in reloading water tank filter screen equipment of nuclear power station contains a plurality of filtering component, converges groove, pipeline header. The confluence groove is used as a rigid structural support of the filter screen equipment and is fixedly arranged above a water taking pit in the built-in refueling water tank through welding connection with a built-in base in the built-in refueling water tank by adopting a frame type design; a plurality of filtering component pass through the fastener as independent filter unit and converge the groove and be connected, converge groove one side and set up the pipeline header and be used for connecting the process line. And the coolant in the built-in refueling water tank flows into a water taking pit and a process pipeline in the built-in refueling water tank through the confluence groove after being filtered by the filtering component.
Preferably, the confluence groove is a structural frame of the filter screen equipment, and is arranged above a water taking pit of the built-in refueling water tank and on a steel cover surface of the side wall.
Preferably, the confluence groove is fixedly connected with an embedded base in the built-in refueling water tank through welding.
Preferably, the filter assembly and the pipe header are connected to the manifold slot by bolts.
Preferably, the filtering component consists of a component box body and a plurality of filter elements; the filter core is array in the subassembly box and closely arranges, adopts draw-in groove and welded mode to be connected between subassembly box and the filter core, and the filter core number that filtering component contains can arrange the requirement according to filter screen whole and required filter area carries out nimble design, and filtering component is independent filter unit to be connected with the groove of converging alone, single filtering component's replacement and change do not influence the whole function of filter screen equipment.
Preferably, the filtering fluid medium flows into the filtering component from the front end opening of each filter element, and flows out from the back of the filtering component after being filtered by each side wall and the bottom of each filter element; the fluid medium flowing from the back of the filter assembly flows directly into the manifold.
Preferably, the bus duct is composed of a support frame and a package cover plate; except for reserving installation spaces of the filtering components and the pipeline header, the circumferential direction and the top of the supporting frame are encapsulated by an encapsulating cover plate to form a tank box structure.
Preferably, the packaging cover plate is connected with the supporting frame and the supporting frame through bolts, and the cover plate on the side surface of the supporting frame can be used as a personnel inlet and outlet of the inner space of the confluence groove after being integrally disassembled; the encapsulation cover plate is provided with reinforcing ribs to enhance structural rigidity.
Preferably, the supporting frame is respectively welded and fixed in the built-in refueling water tank with the reserved base of the side wall and the bottom steel covering surface of the built-in refueling water tank through the lateral support and the base.
Preferably, the pipeline header is formed by combining steel plates, and the steel plates are connected by bolts; the pipe header is provided with a flange hole for connecting a process pipeline.
One or more technical solutions provided by the present application have at least the following technical effects or advantages:
the filter screen equipment covers the upper part of the water taking pit in the built-in refueling water tank, and the coolant in the built-in refueling water tank flows into the water taking pit and the process pipeline in the built-in refueling water tank after being filtered by the filter screen equipment, so that the effects of intercepting and retaining impurities in the coolant and preventing the coolant from entering the water taking pit and the process pipeline are achieved.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiments of the invention and together with the description serve to explain the principles of the invention;
FIG. 1 is a schematic structural view of the filter screen equipment of the refueling water tank built in the nuclear power station;
FIG. 2 is a schematic view of a filter assembly construction;
FIG. 3 is a schematic view of a sink configuration;
FIG. 4 is a schematic view of a support frame;
fig. 5 is a schematic view of a piping header structure.
Detailed Description
In order to make the aforementioned objects, features and advantages of the present invention more clearly understood, the present invention will be described in further detail with reference to the accompanying drawings and detailed description. It should be noted that the embodiments and features of the embodiments of the present application may be combined with each other without conflicting with each other.
In the following description, numerous specific details are set forth in order to provide a thorough understanding of the present invention, however, the present invention may be practiced in other ways than those specifically described herein, and the scope of the present invention is not limited by the specific embodiments disclosed below.
Referring to fig. 1, the filter screen equipment of the refueling water tank of the nuclear power plant is designed in a box-type structure and comprises a filter assembly 1, a confluence groove 2 and a pipeline header 3.
Referring to fig. 1, the collecting tank 2 is a structural frame of the filter screen device, and the collecting tank 2 is installed above a water taking pit of a built-in refueling water tank and on a steel cover surface of a side wall.
Referring to fig. 1, a plurality of filter assemblies 1 and a pipe header 3 are connected to a manifold tank 2 by bolts.
The filter assemblies 1 are independent filter units and are individually connected with the confluence groove 2, and the replacement and the change of the single filter assembly 1 do not affect the whole function of the filter screen device.
The filtering component 1, the confluence groove 2 and the pipeline header 3 are all made of austenitic stainless steel.
Referring to fig. 2, the filter assembly 1 is composed of an assembly box 4 and a plurality of filter elements 5; the filter cores 5 are arranged in the assembly box body 4 in an array type closely, and the assembly box body 4 is connected with the filter cores 5 in a clamping groove and welding mode. The filtering fluid medium flows into the filtering component 1 from the front end opening of each filter element 5, and flows out from the back of the filtering component 1 after being filtered by each side wall and the bottom of each filter element 5; the filter assembly (1) is installed on the confluence groove 2 through bolts as an independent structure, and fluid medium flowing out of the back of the filter assembly (1) directly flows into the confluence groove 2. The number of filter elements 5 contained in the filter assembly 1 can be flexibly designed according to the overall arrangement requirement of the filter screen and the required filter area.
Referring to fig. 3, the bus duct 2 is composed of a support frame 6 and a package cover plate 7; except for the reserved installation space of the filtering component 1 and the pipeline header 3, the circumferential direction and the top of the supporting frame 6 are encapsulated by an encapsulating cover plate 7 to form a tank box structure; the packaging cover plate 7 is connected with the supporting frame 6 through bolts, the packaging cover plate and the supporting frame are of detachable structures, and the cover plate on the side surface of the supporting frame 6 can be used as a personnel inlet and outlet of the inner space of the confluence groove after being integrally detached; the package cover 7 is provided with stiffening ribs to enhance structural rigidity.
Referring to fig. 4, the supporting frame 6 is welded and fixed in the built-in refueling water tank with the reserved base of the steel cover of the side wall and the bottom surface of the built-in refueling water tank through the lateral support 8 and the base 9. The supporting frame 6 can be flexibly designed according to the requirement of the installation space in the internal replacement material water tank and the requirement of the arrangement of the embedded base.
Referring to fig. 5, the pipe header 3 is formed by combining steel plates which are connected by bolts; the pipeline header 3 is provided with a flange hole for connecting a process pipeline, and the connecting surface of the process pipeline is provided with a reinforcing rib for reinforcing the structural rigidity of the header.
While the preferred embodiments of the present invention have been described, additional variations and modifications in those embodiments may occur to those skilled in the art once they learn of the basic inventive concepts. It is therefore intended that the appended claims be interpreted as including the preferred embodiment and all such alterations and modifications as fall within the scope of the invention.
It will be apparent to those skilled in the art that various changes and modifications may be made without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims and their equivalents, the present invention is also intended to include such modifications and variations.

Claims (10)

1. The utility model provides a built-in reloading water tank filter screen equipment of nuclear power station, its characterized in that, equipment includes:
the filter assemblies, the confluence groove and the pipeline header are arranged in the pipeline; the confluence groove is arranged above a water taking pit in the built-in refueling water tank; the plurality of filtering components are used as independent filtering units and are connected with the confluence groove through fasteners, and a pipeline header is arranged on one side of the confluence groove and is used for connecting a process pipeline; after being filtered by the filtering component, the coolant in the built-in refueling water tank flows into a water taking pit in the built-in refueling water tank through the confluence groove and flows into a process pipeline through a pipeline header.
2. The nuclear power plant refueling water tank strainer device as recited in claim 1 wherein the manifold slot is a structural frame of the strainer device, the manifold slot being mounted above the refueling water tank pit and on the steel cladding of the sidewall.
3. The filter screen equipment for the built-in refueling water tank of the nuclear power plant as recited in claim 1, wherein the confluence groove is fixedly connected with an embedded base in the built-in refueling water tank through welding.
4. The nuclear power plant built-in refueling water tank strainer device according to claim 1, wherein the filter assembly and the pipe header are connected to the manifold tank by bolts.
5. The filter screen device of the built-in refueling water tank of the nuclear power plant as recited in claim 1, wherein the filter assembly is composed of an assembly box body and a plurality of filter elements; the filter cores are arranged in the assembly box body in an array type closely, and the assembly box body is connected with the filter cores in a clamping groove and welding mode.
6. The filter screen device for the built-in refueling water tank of the nuclear power plant as recited in claim 5, wherein the filtering fluid medium flows into the filtering assembly from the front end opening of each filter element, and flows out from the back of the filtering assembly after being filtered by each side wall and the bottom of each filter element; the fluid medium flowing from the back of the filter assembly flows directly into the manifold.
7. The built-in refueling water tank filter screen device for nuclear power plants as claimed in claim 1, wherein the confluence groove is composed of a support frame and a packaging cover plate; except for reserving installation spaces of the filtering components and the pipeline header, the circumferential direction and the top of the supporting frame are encapsulated by an encapsulating cover plate to form a tank box structure.
8. The filter screen device of the built-in refueling water tank of the nuclear power plant as recited in claim 7, wherein the encapsulating cover plate is connected with the supporting frame and the encapsulating cover plate are connected with each other by bolts, and the side cover plate of the supporting frame can be used as a personnel inlet and outlet of the inner space of the confluence groove after being integrally disassembled; the encapsulation cover plate is provided with reinforcing ribs to enhance structural rigidity.
9. The filter screen equipment for the built-in refueling water tank of the nuclear power plant as recited in claim 7, wherein the support frame is welded and fixed in the built-in refueling water tank through a lateral support and a base with a reserved base of steel cladding of the side wall and the bottom surface of the built-in refueling water tank respectively.
10. The filter screen equipment for the built-in refueling water tank of the nuclear power plant as recited in claim 1, wherein the pipeline header is formed by combining steel plates, and the steel plates are connected by bolts; the pipe header is provided with a flange hole for connecting a process pipeline.
CN201921796569.8U 2019-10-24 2019-10-24 Built-in reloading water tank filter screen equipment of nuclear power station Active CN211585391U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201921796569.8U CN211585391U (en) 2019-10-24 2019-10-24 Built-in reloading water tank filter screen equipment of nuclear power station

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201921796569.8U CN211585391U (en) 2019-10-24 2019-10-24 Built-in reloading water tank filter screen equipment of nuclear power station

Publications (1)

Publication Number Publication Date
CN211585391U true CN211585391U (en) 2020-09-29

Family

ID=72586298

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201921796569.8U Active CN211585391U (en) 2019-10-24 2019-10-24 Built-in reloading water tank filter screen equipment of nuclear power station

Country Status (1)

Country Link
CN (1) CN211585391U (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113299412A (en) * 2021-04-29 2021-08-24 中国核电工程有限公司 Compromise emergent reactor core cooling system filter of filtering and drainage function

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113299412A (en) * 2021-04-29 2021-08-24 中国核电工程有限公司 Compromise emergent reactor core cooling system filter of filtering and drainage function
CN113299412B (en) * 2021-04-29 2022-02-18 中国核电工程有限公司 Compromise emergent reactor core cooling system filter of filtering and drainage function

Similar Documents

Publication Publication Date Title
US20110215059A1 (en) Filter medium for strainers used in nuclear reactor emergency core cooling systems
KR20080059631A (en) Filter medium for strainers used in nuclear reactor emergency core cooling systems
CN103028285B (en) Filter system for built-in containment refueling water storage tank
KR101025706B1 (en) Strainer filtering apparatus including filtered tube
US8611488B2 (en) Debris exclusion and retention device for a fuel assembly
CN104919534A (en) Apparatus and method for removing the upper internals from a nuclear reactor pressurized vessel
CN211585391U (en) Built-in reloading water tank filter screen equipment of nuclear power station
CA3068570A1 (en) Active pit tank strainer of a nuclear power plant
CN209297865U (en) A kind of dust-proof guard shield of dry-type transformer
JP6266466B2 (en) Debris reduction system in reactor safety system
CN103047129A (en) Filter at safety system pump suction inlet inside replacement material water tank inside nuclear power plant
CN210674453U (en) Box-type filter element structure of special safety system for nuclear power station
CN210193441U (en) Tank opening structure of water treatment pressure tank
CN106782691A (en) The built-in material-changing water tank of nuclear power plant containment shell
CN102013277A (en) Decay tank
RU2778712C1 (en) Tank for garbage filtration and collection
JP3315572B2 (en) Fuel assembly and debris filter and lower tie plate
CN215427691U (en) Circle font formula filter equipment that sinks for nuclear power station
CN116487077A (en) Built-in material-changing water tank of containment
CN104123971A (en) Nuclear power plant radioactive effluent disposal system
CN217613277U (en) External filter for high-pressure cooling water of once-through boiler starting recirculation pump
CN113299412B (en) Compromise emergent reactor core cooling system filter of filtering and drainage function
CN215742002U (en) Oil filtering device without disassembling and washing
CN216418468U (en) Filtering device
CN202025538U (en) Decay tank

Legal Events

Date Code Title Description
GR01 Patent grant
GR01 Patent grant