CN204884581U - A white -out system that is used for active waste heat discharge system of nuclear power station secondary side non - - Google Patents

A white -out system that is used for active waste heat discharge system of nuclear power station secondary side non - Download PDF

Info

Publication number
CN204884581U
CN204884581U CN201520424647.7U CN201520424647U CN204884581U CN 204884581 U CN204884581 U CN 204884581U CN 201520424647 U CN201520424647 U CN 201520424647U CN 204884581 U CN204884581 U CN 204884581U
Authority
CN
China
Prior art keywords
white
containment
house steward
nuclear power
heat removal
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
CN201520424647.7U
Other languages
Chinese (zh)
Inventor
李军
姜百华
叶欣楠
吴永重
赵嘉明
盛美玲
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.)
China Nuclear Power Engineering Co Ltd
Original Assignee
China Nuclear Power Engineering Co Ltd
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 China Nuclear Power Engineering Co Ltd filed Critical China Nuclear Power Engineering Co Ltd
Priority to CN201520424647.7U priority Critical patent/CN204884581U/en
Application granted granted Critical
Publication of CN204884581U publication Critical patent/CN204884581U/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • 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

Abstract

The utility model relates to a white -out system that is used for active waste heat discharge system of nuclear power station secondary side non -, including setting up white -out house steward (6) outside the containment, the one end of white -out house steward (6) is sealed, and the other end is linked together with the active outer low reaches of the waste heat discharge security of system shell pipeline of secondary side non -, between the pipeline of the outer upper reaches of the active waste heat discharge security of system shell of white -out house steward (6) and secondary side non - with all be equipped with hydrophobic pipeline between heat exchanger (5) outside the active waste heat discharge security of system shell of white -out house steward (6) and secondary side non -. The utility model discloses a white -out system, equipment and/or pipeline white -out problem when having solved the maintenance of the active waste heat discharge system of nuclear power station secondary side non - to make during most equipment or pipeline white -out log raft go into the steam generator to the containment in, reach final multiplexing purpose, reduced nuclear power station waste liquid production volume.

Description

For the white-out system of nuclear power station Passive residual heat removal system
Technical field
The utility model belongs to hydrophobic exhaust field, is specifically related to a kind of white-out system for nuclear power station Passive residual heat removal system.
Background technology
The domestic generation Ⅲ nuclear power unit design with independent intellectual property right has Passive residual heat removal system.This system is used under accident conditions, rely on natural force to realize implementing cooling to steam generator secondary side.The non-active cooling that Passive residual heat removal system is arranged on the residual heat removal exchanger in passive containment thermal conduction system heat-exchanging water tank and the pipeline that is connected with evaporator secondary side realizes evaporator secondary side primarily of one.
Passive residual heat removal system comprises the major equipment of residual heat removal exchanger, is arranged in outer more than the absolute altitude+40m of containment, is therefore outside equipped with part white-out point for draining during system overhaul at containment.Consider the actual arrangement situation of Passive residual heat removal system containment external equipment, adopt and special drain line is set there is larger difficulty on the implementation discharged to traditional white-out mode of hydrophobic exhaust system, no matter be set up containment penetration drain line is imported in containment, or by drain line along containment outer wall, introduce in other nuclear island factory buildings through other factory buildings and all need to pay very large cost.In addition, according to the design of Passive residual heat removal system, the hydrophobic reusable identical with the water quality of steam generator secondary side of this system, entering hydrophobic exhaust system not only wastes and can increase nuclear power station waste liquid amount.
The utility model aims to provide a kind of white-out system for nuclear power station Passive residual heat removal system.This system, by rationally arranging drain line, by flow by gravity, is made the hydrophobic of each white-out point place be back in containment through containment penetration by the existing pipeline of Passive residual heat removal system self, and finally enters in steam generator.
Utility model content
For the defect existed in prior art, the utility model provides a kind of white-out system for nuclear power station Passive residual heat removal system, this system is by rationally arranging drain line, pass through flow by gravity, solve equipment when Heat Discharging System of Chinese overhauls and/or pipeline white-out problem, and make most equipment and/or pipeline water drainage be drained in steam generator, reach finally multiplexing object, decrease nuclear power station waste liquid generation.
For reaching above object, the technical solution adopted in the utility model is: provide a kind of white-out system for nuclear power station Passive residual heat removal system, comprise the white-out house steward be arranged on outside containment, one end of described white-out house steward is closed, and the other end is connected with the outer downstream line of Passive residual heat removal system containment; Hydrophobic pipeline is provided with between heat exchanger outside described white-out house steward and Passive residual heat removal system containment.
Further, hydrophobic pipeline is provided with between described white-out house steward and the outer upstream line of Passive residual heat removal system containment.
Further, hydrophobic pipeline is respectively equipped with between the heat exchanger upper cover outside described white-out house steward and residual heat removal system containment and between the heat exchanger low head of white-out house steward and residual heat removal system.
Further, described white-out house steward is arranged in absolute altitude lower than each white-out point outside containment.
Further, described white-out house steward is provided with isolation valve.
Further, every bar hydrophobic pipeline is provided with isolation valve.
Further, in described Heat Discharging System of Chinese containment, downstream line minimum point place is provided with hydrophobic pipeline, and described hydrophobic pipeline is provided with isolation valve.
Advantageous Effects of the present utility model is:
The white-out system of the Heat Discharging System of Chinese that the utility model provides, this white-out system is by rationally arranging drain line, pass through flow by gravity, make the hydrophobic by the existing pipeline of Heat Discharging System of Chinese self of each white-out point place, be back in containment through containment penetration, and finally enter in steam generator.Thus, equipment when the utility model solves the domestic generation Ⅲ nuclear power unit Passive residual heat removal system maintenance with independent intellectual property right and/or pipeline white-out problem, and make most equipment and/or pipeline water drainage be drained in steam generator, reach finally multiplexing object, decrease nuclear power station waste liquid generation.
Accompanying drawing explanation
Fig. 1 is the structural representation of the white-out system of the utility model Heat Discharging System of Chinese.
In figure:
1-evaporator 2,4,7,8,9-isolation valve 3-containment penetration
5-heat exchanger 6-white-out house steward
Embodiment
Below in conjunction with accompanying drawing, embodiment of the present utility model is described in further detail.
As shown in Figure 1, it is the white-out system for nuclear power station Passive residual heat removal system provided by the utility model, comprise and be arranged on the outer white-out house steward 6 of containment, one end of this white-out house steward 6 is closed, and the other end is connected with the outer downstream line low spot place of Heat Discharging System of Chinese containment.Between the outer upstream line fluid-tight place N03 of white-out house steward 6 and Heat Discharging System of Chinese containment, between white-out house steward 6 and the outer residual heat removal exchanger 5 upper cover N04 place of containment and be equipped with hydrophobic pipeline N03 to N11, N04 to N12, N05 to N13 between white-out house steward 6 and residual heat removal exchanger 5 low head place N05, equipment and/or pipeline white-out problem during for solving Heat Discharging System of Chinese maintenance.
Wherein, every bar hydrophobic pipeline is provided with isolation valve 7,8,9, for the isolation of hydrophobic pipeline and system superintendent's line.White-out house steward 6 is provided with main pipe line isolation valve 2, for the isolation of white-out house steward 6 with system superintendent road, guarantee when a certain hydrophobic pipeline isolation valve 7,8, when 9 inefficacies or maloperation, Passive residual heat removal system residual heat removal exchanger 5 there will not be bypass accident.
White-out house steward 6 arranges that absolute altitude is lower than containment outer each white-out point N03, N04, N05, like this, is collected to white-out house steward 6 by means of gravity by the draining in each hydrophobic pipeline N03 to N11, N04 to N12, N05 to N13.
In Passive residual heat removal system containment, downstream line minimum point place is provided with hydrophobic pipeline N09 to N10.Pipeline N07 to N08 for being arranged in containment below evaporator 1 entrance absolute altitude is emptying.This hydrophobic pipeline N09 to N10 is provided with hydrophobic pipeline isolation valve 4, for the isolation of hydrophobic pipeline N09 to N10 and the isolation of main pipeline.
Thus, the hydrophobic pipeline N03 to N11 outside containment, N04 to N12, N05 to N13 respectively white-out house steward 6 outer with containment are connected, and collect containment each hydrophobic pipeline outer collect the draining of coming by white-out house steward.The outer white-out house steward of containment is connected with the outer downstream line low spot place N06 of Passive residual heat removal system containment, be beneficial to by means of gravity, outer for containment white-out house steward 6 is collected be hydrophobicly transmitted back to the outer downstream line of Passive residual heat removal system containment, and rely on gravity to be back in containment through containment penetration 3 by the pipeline of system self, and then be back to N06 to N01 in steam generator 1, and complete multiplexing eventually through steam generator blowdown system.
Obviously, those skilled in the art can carry out various change and modification to the utility model and not depart from spirit and scope of the present utility model.Like this, if belong within the scope of the utility model claim and equivalent technology thereof to these amendments of the present utility model and modification, then the utility model is also intended to comprise these change and modification.

Claims (7)

1. the white-out system for nuclear power station Passive residual heat removal system, it is characterized in that: comprise the white-out house steward (6) be arranged on outside containment, one end of described white-out house steward (6) is closed, and the other end is connected with the outer downstream line of Passive residual heat removal system containment; Hydrophobic pipeline is provided with between heat exchanger (5) outside described white-out house steward (6) and Passive residual heat removal system containment.
2. as claimed in claim 1 for the white-out system of nuclear power station Passive residual heat removal system, it is characterized in that: between described white-out house steward (6) and the outer upstream line of Passive residual heat removal system containment, be provided with hydrophobic pipeline.
3. as claimed in claim 1 or 2 for the white-out system of nuclear power station Passive residual heat removal system, it is characterized in that: between heat exchanger (5) upper cover outside described white-out house steward (6) and residual heat removal system containment and between heat exchanger (5) low head of white-out house steward (6) and residual heat removal system, be respectively equipped with hydrophobic pipeline.
4., as claimed in claim 3 for the white-out system of nuclear power station Passive residual heat removal system, it is characterized in that: described white-out house steward (6) is arranged in absolute altitude lower than each white-out point outside containment.
5., as claimed in claim 4 for the white-out system of nuclear power station Passive residual heat removal system, it is characterized in that: described white-out house steward (6) is provided with isolation valve (2).
6. as claimed in claim 5 for the white-out system of nuclear power station Passive residual heat removal system, it is characterized in that: every bar hydrophobic pipeline is provided with isolation valve (8,7,9).
7. as claimed in claim 6 for the white-out system of nuclear power station Passive residual heat removal system, it is characterized in that: in described Heat Discharging System of Chinese containment, downstream line minimum point place is provided with hydrophobic pipeline, described hydrophobic pipeline is provided with isolation valve (4).
CN201520424647.7U 2015-06-18 2015-06-18 A white -out system that is used for active waste heat discharge system of nuclear power station secondary side non - Active CN204884581U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201520424647.7U CN204884581U (en) 2015-06-18 2015-06-18 A white -out system that is used for active waste heat discharge system of nuclear power station secondary side non -

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201520424647.7U CN204884581U (en) 2015-06-18 2015-06-18 A white -out system that is used for active waste heat discharge system of nuclear power station secondary side non -

Publications (1)

Publication Number Publication Date
CN204884581U true CN204884581U (en) 2015-12-16

Family

ID=54828933

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201520424647.7U Active CN204884581U (en) 2015-06-18 2015-06-18 A white -out system that is used for active waste heat discharge system of nuclear power station secondary side non -

Country Status (1)

Country Link
CN (1) CN204884581U (en)

Similar Documents

Publication Publication Date Title
CN203276869U (en) Steam generator sewage drainage system preventing overflow of steam generator
CN203848705U (en) Exhausted steam recycling system
CN103531256B (en) The non-active cooling system of presurized water reactor prestressed concrete containment vessel
CN204884581U (en) A white -out system that is used for active waste heat discharge system of nuclear power station secondary side non -
CN203503305U (en) Cooling and treatment system for refueling pool and spent fuel pool of reactor
CN205279052U (en) Concrete pipe pile evaporates and presses surplus vapour recovery purification structure of cauldron
CN205900113U (en) A collecting system for collecting nuclear power station main pump low pressure bearing seal leakage water
CN209843263U (en) Passive accident waste heat discharging system for sodium-cooled fast reactor intermediate circuit
CN202855323U (en) Filtering and gathering system and steam and atmosphere discharging system
CN210624494U (en) High-temperature heat storage type steam boiler
CN209128091U (en) A kind of integration apparatus of ion-exchanger and resin catcher
CN211452951U (en) Environment-friendly energy-saving boiler water sampler
CN204242602U (en) Secondary side passive residual heat guiding system
CN209113829U (en) A kind of natural gas collecting device with gas collection, separation and flash distillation function
CN103778978B (en) Integral reactor main pump drainage for overhaul and Residual heat removal method
CN207227051U (en) A kind of oxygen-eliminating device without a head
CN202101458U (en) Utilization device for water in solar energy water pipes
CN201636529U (en) Fully-enclosed collecting device for gas condensed liquor
CN214096703U (en) Low temperature sample frame water sample drainage recovery unit
CN205580216U (en) Rotary kiln waste heat recovery utilizes system
CN207421770U (en) The rain dirt separator of top of gas cabinet
CN206945344U (en) A kind of carbonated drink sampling stand draining recovery system
CN210398410U (en) Drainage discharging device
CN203454084U (en) Device preventing brimming of vapor generators
CN220646042U (en) Recovery system for steam turbine drainage and feed pump cooling water backwater

Legal Events

Date Code Title Description
C14 Grant of patent or utility model
GR01 Patent grant