CN201522858U - Cable penetrating device for loss of coolant accident test containers in nuclear power plant - Google Patents

Cable penetrating device for loss of coolant accident test containers in nuclear power plant Download PDF

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Publication number
CN201522858U
CN201522858U CN2009202427665U CN200920242766U CN201522858U CN 201522858 U CN201522858 U CN 201522858U CN 2009202427665 U CN2009202427665 U CN 2009202427665U CN 200920242766 U CN200920242766 U CN 200920242766U CN 201522858 U CN201522858 U CN 201522858U
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CN
China
Prior art keywords
plug
end plate
runs
pad
penetrating
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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.)
Expired - Lifetime
Application number
CN2009202427665U
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Chinese (zh)
Inventor
王广金
周缘
周天
郑兰疆
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Nuclear Power Institute of China
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Nuclear Power Institute of China
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Priority to CN2009202427665U priority Critical patent/CN201522858U/en
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Publication of CN201522858U publication Critical patent/CN201522858U/en
Anticipated expiration legal-status Critical
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    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • YGENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The utility model provides a cable penetrating device for a loss of coolant accident test container in a nuclear power plant, which consists of a penetrating mandrel, an end plate flange, a supporting plate and a supporting rod, wherein the penetrating mandrel, the end plate flange, the supporting plate and the supporting rod are connected detachably. The penetrating mandrel consists of an insulating coated conductor, a sealing module and a protective sleeve, the sealing module and the protective sleeve are sleeved on the outer surface of the insulating coated conductor, one end of the penetrating mandrel penetrates through the end plate flange and is sealed with the same via a pressing ring and a metal ferrule, the penetrating mandrel is then fixed on the end plate flange via a gland nut, and the other end of the penetrating mandrel penetrates through the supporting plate and is circumferentially fixed on the same. One end of the supporting rod is connected with the end plate flange while the other end is fixed on the supporting plate. The cable penetrating device is simple in structure, stable and reliable in performance, high in universality and convenient in detachment, can maintain boundary integrity and electrical continuity of the pressure container.

Description

Nuclear power plant's loss of fluid test container cable penetration device
Technical field
The utility model relates to a kind of cable penetration device, be specifically related to a kind of nuclear power plant's loss of-coolant accident (LOCA) (LOCA) test chamber that is specifically designed to, for providing power, control or instrument cable, the test chamber internal unit runs through the passage of pressure vessel, constitute the test chamber pressure barrier, and can satisfy the cable penetration device that tolerates internal tank environment, pressure-bearing, airtight and electric performance requirement such as complete.
Background technology
Loss of-coolant accident (LOCA) (LOCA) test chamber is the simulation nuclear power plant thermal technology in the containment and chemical environment during loss of-coolant accident (LOCA), during the accident and after the accident, whether can follow procedure requires the special-purpose test chamber of normal steady operation in order to test nuclear level equipment.Therefore, require in carrying out the LOCA process of the test, the passage of power or signal transmission is provided for the nuclear level equipment of test.
Usually, power or signal cable run through directly perforate on the outside flange of test chamber of the many employings of LOCA test chamber, as the hole of cable penetration shell of tank; According to by the difference of test equipment, adopt the direct perforated holes of cable of different size, link to each other with testing equipment; The sealing of cable and perforated holes adopts silicon rubber or epoxy resin to carry out shutoff, and by the gland nut attached cable.In use, the sealing of silicon rubber or epoxy resin needs if occur leaking, need use the sealant shutoff by carrying out pressure and sealing detection with test chamber integral body repeatedly, has increased the workload of installing; Silicon rubber or epoxy sealing mainly rely on the cementability of sealant itself, because the variation of temperature and pressure in the LOCA process of the test causes seal failure easily.Simultaneously, bring the difference of cable type selecting, need the outside flange of band different size hole to cooperate with it, make outside flange frequently change, cause a large amount of wastes because of the difference of each testing equipment.Therefore, traditional cable penetration mode has been brought great inconvenience to experiment work.
Summary of the invention
The purpose of this utility model is to provide a kind of simple in structure, dependable performance, nuclear power plant's loss of fluid test container cable penetration device that can use on the LOCA test chamber.
The utility model is achieved in that
A kind of nuclear power plant loss of fluid test container cable penetration device, comprise by insulation coating conductor and its outside surface and be with the plug that runs through that seal modules and protective casing constitute, an end that runs through plug passes end plate flanges, with hold-down ring and metal ferrule and end plate flanges sealing, to run through plug by gland nut is fixed on the end plate flanges, it is characterized in that: the other end that runs through plug passes back up pad, has tapped through hole on the back up pad, runs through plug and circumferentially is fixed on the back up pad; One end of support bar is connected with end plate flanges, and the other end is fixed on the back up pad.
Its supplementary features are:
The described plug that runs through has many, and its external diameter is unified.
The described insulation coating conductor that runs through plug can prolong several meters, and its prolongation is with stainless steel ripple flexible pipe.
Effect of the present utility model is: owing to run through the standardization of plug, be convenient to the dismounting and the exchange of assembly; Simple in structure, dependable performance, highly versatile satisfy high temperature resistant hydrolysis, resistance to chemical attack, specific (special) requirements such as withstand voltage and airtight and have good electrical continuity.
Description of drawings
Fig. 1 is the structural representation of cable penetration device of the present utility model.
Fig. 2 is the structural representation that runs through plug of the utility model through-going device.
Fig. 3 is the use wiring layout of cable penetration device of the present utility model.
Among the figure: 1. stainless steel ripple flexible pipe; 2. run through plug; 3. gland nut; 4. hold-down ring; 5. cutting ferrule; 6. end plate flanges; 7. back up pad; 8. holding screw; 9. support bar; 10. nut; 11. plain washer; 12. blind plugging; 13. insulation coating conductor; 14. seal modules; 15. protective casing; 16. external cabling case; 17. through-going device body; 18.LOCA test chamber; 19. back panel wiring case
Embodiment
As shown in Figure 1 and Figure 2, the utility model is formed by running through plug 2, end plate flanges 6, back up pad 7 and support bar 9, all adopts between them to removably connect.Running through plug 2 adopts continuous balanced extrusion forming process to make by insulation coating conductor 13, seal modules 14 and protective casing 15 assembling backs.Seal modules 14 is enclosed within the outside of insulation coating conductor 13, and protective casing 15 is enclosed within on the seal modules 14.An end that runs through plug 2 passes end plate flanges 6, with hold-down ring 4 and metal ferrule 5 and end plate flanges 6 sealings, provides the sealing pretightning force will run through plug 2 by gland nut 3 and is fixed on the end plate flanges 6, and the other end passes back up pad 7.Have tapped through hole on the back up pad 7, it is circumferentially fixing to run through plug 2 by holding screw 8.One end of support bar 9 is connected with end plate flanges 6 by screw thread, and the other end passes back up pad 7, is fixed on the back up pad 7 by plain washer 11 and nut 10.
Insulation coating conductor 13 and seal modules 14 employing polysulfones or polyetheretherketone, polyethersulfone, polyimide.Insulation coating conductor 13 can prolong several meters according to pressure vessel physical size and installation site, its prolongation is with stainless steel ripple flexible pipe 1, with experimental enviroment in the insulating coating that prevents from the use to scratch lead and the container to the destruction of insulation course, thereby influence electrical insulation properties.Run through plug 2 and have many, its external diameter is unified.Have a plurality of holes of running through plug 2 that are used to install on the end plate flanges 6, remaining standby installation duct can be used in order to expanding by blind plugging 12 shutoff.
The use wiring layout of cable penetration device as shown in Figure 3, end plate flanges 6 is connected through-going device body 17 by bolt with LOCA test chamber 18.Inside cable and external cable by the terminal in line nose or external cabling case 16 and the back panel wiring case 19 with run through plug 2 and be communicated with.
Cable penetration device of the present utility model is under design pressure, to maximum gas slip≤1 * 10 of dry helium gas -6Atmcm 3/ s; Insulation resistance under direct current 500V (minimum value) is greater than 10 9Ω.

Claims (3)

1. nuclear power plant's loss of fluid test container cable penetration device, comprise by what insulation coating conductor (13) and its outside surface were with seal modules (14) and protective casing (15) formation and run through plug (2), an end that runs through plug (2) passes end plate flanges (6), with hold-down ring (4) and metal ferrule (5) and end plate flanges (6) sealing, to run through plug (2) by gland nut (3) is fixed on the end plate flanges (6), it is characterized in that: the other end that runs through plug (2) passes back up pad (7), back up pad has tapped through hole on (7), runs through plug (2) and circumferentially is fixed on the back up pad (7); One end of support bar (9) is connected with end plate flanges (6), and the other end is fixed on the back up pad (7).
2. according to the described cable penetration device of claim 1, it is characterized in that: the described plug (2) that runs through has many, and its external diameter is unified.
3. according to claim 1 or 2 described cable penetration devices, it is characterized in that: the described insulation coating conductor (13) that runs through plug (2) can prolong several meters, and its prolongation is with stainless steel ripple flexible pipe (1).
CN2009202427665U 2009-10-27 2009-10-27 Cable penetrating device for loss of coolant accident test containers in nuclear power plant Expired - Lifetime CN201522858U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN2009202427665U CN201522858U (en) 2009-10-27 2009-10-27 Cable penetrating device for loss of coolant accident test containers in nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN2009202427665U CN201522858U (en) 2009-10-27 2009-10-27 Cable penetrating device for loss of coolant accident test containers in nuclear power plant

Publications (1)

Publication Number Publication Date
CN201522858U true CN201522858U (en) 2010-07-07

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Family Applications (1)

Application Number Title Priority Date Filing Date
CN2009202427665U Expired - Lifetime CN201522858U (en) 2009-10-27 2009-10-27 Cable penetrating device for loss of coolant accident test containers in nuclear power plant

Country Status (1)

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CN (1) CN201522858U (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102768867A (en) * 2012-07-18 2012-11-07 安徽省鑫源达有色金属材料有限公司 Electrical penetration piece with ceramic sealing electrode
CN104332190A (en) * 2014-11-19 2015-02-04 中国核动力研究设计院 Mineral insulating assembly, preparation method and safety device having mineral insulating assembly
CN106128523A (en) * 2016-08-10 2016-11-16 长江勘测规划设计研究有限责任公司 A kind of underground nuclear power station fluid-tight electrical penetration system

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN102768867A (en) * 2012-07-18 2012-11-07 安徽省鑫源达有色金属材料有限公司 Electrical penetration piece with ceramic sealing electrode
CN104332190A (en) * 2014-11-19 2015-02-04 中国核动力研究设计院 Mineral insulating assembly, preparation method and safety device having mineral insulating assembly
CN104332190B (en) * 2014-11-19 2017-04-12 中国核动力研究设计院 Mineral insulating assembly, preparation method and safety device having mineral insulating assembly
CN106128523A (en) * 2016-08-10 2016-11-16 长江勘测规划设计研究有限责任公司 A kind of underground nuclear power station fluid-tight electrical penetration system

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Granted publication date: 20100707