CN106024076A - Device for reducing risk of pressure relief tank compartment of nuclear power plant - Google Patents

Device for reducing risk of pressure relief tank compartment of nuclear power plant Download PDF

Info

Publication number
CN106024076A
CN106024076A CN201610329850.5A CN201610329850A CN106024076A CN 106024076 A CN106024076 A CN 106024076A CN 201610329850 A CN201610329850 A CN 201610329850A CN 106024076 A CN106024076 A CN 106024076A
Authority
CN
China
Prior art keywords
release case
power plant
nuclear power
containment
pressure relief
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.)
Granted
Application number
CN201610329850.5A
Other languages
Chinese (zh)
Other versions
CN106024076B (en
Inventor
石雪垚
刘建平
王辉
陈巧艳
周喆
雷宁博
孙婧
李汉辰
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 CN201610329850.5A priority Critical patent/CN106024076B/en
Publication of CN106024076A publication Critical patent/CN106024076A/en
Application granted granted Critical
Publication of CN106024076B publication Critical patent/CN106024076B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/001Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices against explosions, e.g. blast shields
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C9/00Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004Pressure suppression
    • 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

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The invention relates to a device for reducing risk of a pressure relief tank compartment of a nuclear power plant. The device comprises an exhaust pipe (2) connected with a pressure relief tank burst valve (7) through a connecting pipe (12), wherein the exhaust pipe (2) extends to an upper space in a reactor containment, and an exhaust port of the exhaust pipe (2) is located in the upper space in the reactor containment and is away from the containment wall surface. The device is simple in structure, low in manufacturing cost, convenient to mount and maintain and capable of leading vapor and hydrogen exhausted by a pressure relief tank to the large space in the containment, so that aggregation of hydrogen in the pressure relief tank compartment is prevented, and failure of the containment due to explosion of local hydrogen is prevented.

Description

A kind of device for reducing nuclear power plant's release case compartment risk
Technical field
The invention belongs to nuclear plant safety System Configuration Technique field, be specifically related to a kind of for reducing core The device of power plant's release case compartment risk.
Background technology
Release case is nuclear power station for collecting the device of the steam of primary Ioops relief valve discharge, such as Fig. 1 Shown in, release case 6 is usually provided in the release case compartment 5 of containment middle and lower part, and release case 6 connects Being connected to pressure relief pipeline 10, pressure relief pipeline 10 is connected with manostat 8, additionally, unload by relief valve 9 Pressure case 6 top is also associated with release case explosive valve 7 (see Fig. 3).Under design basis accident, one time When road occurs transient state or minor break accident, primary Ioops pressure rises, and exceedes the safety on manostat 8 After the unlatching pressure of valve 9, relief valve 9 automatically turns on, thus primary Ioops is cooled down water and passes through relief tube Road 10 is emitted into release case 6.After nuclear power plant occurs major accident, in order to avoid primary Ioops is at high pressure Lower generation pressure vessel lost efficacy, and pressurizer safety valve to be passed through or fast pressure relief valve carry out one time Road release, during this, primary Ioops cryogen discharge is in release case 6.Release case 6 can be by one Quantitative water, steam are maintained in release case 6, it is to avoid carry active primary Ioops cooling water to enter Enter containment.
But, when release case 6 due to internal pressure too high time, release case explosive valve 7 meeting at its top Automatically open up, by primary Ioops cryogen discharge to containment.During major accident, due to mistake The zirconium cladding of heat can react with steam generation zirconium water, can produce substantial amounts of hydrogen, and these hydrogen pass through After pressurizer safety valve or fast pressure relief valve enter release case 6, entered by release case explosive valve 7 The release case compartment 5 at release case 6 place.Owing to release case compartment 5 is positioned at containment middle and lower part, empty The air-flow general character is poor, higher density of hydrogen occurs, it is possible to send out in therefore causing release case compartment 5 The combustion of hydrogen of raw local even explodes, and then threatens the integrity of containment, causes a large amount of radioactivity Material is to Environment release.
Summary of the invention
For defect present in prior art, it is an object of the invention to provide a kind of for reducing nuclear power Factory's release case compartment combustion of hydrogen, the device of risk of explosion, this apparatus structure is simple, and cost is low, just Safeguard in installing, it is possible to the steam, the hydrogen that are discharged by release case are directed to containment large space, keep away Exempting from hydrogen gathering at release case compartment, the containment preventing localized hydrogen gas blast from causing lost efficacy.
For reaching object above, the technical solution used in the present invention is: one is used for reducing nuclear power plant and unloads The device of pressure case compartment risk, wherein, it is anti-that the release case compartment for placing release case is located at nuclear power plant Answering the middle and lower part of heap containment, described release case connects has pressure relief pipeline, pressure relief pipeline to pass through safety Valve is connected with manostat, and release box top is also associated with release case explosive valve, and described being used for reduces core The device of power plant's release case compartment risk includes the row being connected by connecting tube with release case explosive valve top Feed channel, described discharge duct extends to the upper space in containment vessel, and described exhaustor The air vent in road is positioned at containment vessel upper space and away from containment wall.
Further, connecting tube bottom is connected with explosive valve, and adpting flange and aerofluxus are passed through in connecting tube top Pipeline is connected.
Further, the air vent of described discharge duct is provided with cover plate.
Further, the structure wall that discharge duct is fixed in containment by some pipeline support assemblies On.
The present invention provide for the device reducing nuclear power plant's release case compartment risk can eliminate due to The hydrogen of release case compartment gathers the hydrogen local caused and fires risk, and this apparatus structure is simple, Cost is low, it is simple to installs and safeguards, can either apply and newly-designed nuclear power plant, it is also possible to for built Become the technological transformation of nuclear power plant, thus improve the safety of nuclear power plant.
Accompanying drawing explanation
Fig. 1 is the knot of a kind of device for reducing nuclear power plant's release case compartment risk that the present invention provides Structure schematic diagram;
Fig. 2 is the connection diagram of discharge duct in Fig. 1, connecting tube and release case explosive valve;
Fig. 3 is the connection diagram of existing release case explosive valve and release case.
Detailed description of the invention
The invention will be further described with detailed description of the invention below in conjunction with the accompanying drawings.
As described in Figure 1, the release case that the release case 6 that the present invention relates to is located in containment vessel every Between in 5, release case 6 connects and has release pipeline 10, release pipeline 10 is by relief valve 9 and steady Depressor 8 is connected, and release case 6 top is also associated with release case explosive valve 7.
A kind of device for reducing nuclear power plant's release case compartment risk that the present invention provides includes by even The discharge duct 2 that adapter 12 is connected with release case explosive valve 7, described discharge duct 2 extends to reaction Upper space in heap containment, the air vent of described discharge duct 2 is positioned at containment vessel top Space and away from containment wall.
In the present invention, connecting tube 12 bottom is connected with release case explosive valve 7.Connecting tube 12 top leads to Cross adpting flange 1 to be connected with discharge duct 2, convenient maintenance.
It addition, cover plate 3 can be set on the air vent of discharge duct 2, prevent shower water and foreign body from entering row Feed channel 2.
Under preferable case, the discharge duct 2 in the present invention can be fixed by some pipeline support assemblies 4 On structure wall 11 in containment, prevent to cause owing to release case explosive valve 7 sprays Piping displacement.
Under nuclear power station is properly functioning, the cover plate 3 of discharge duct 2 port of export is closed.Under accident conditions, After release case explosive valve 7 is opened, substantial amounts of steam, hydrogen are entered by release case explosive valve 7 Discharge duct 2, cover plate 3 automatically opens up under gas shock simultaneously, by substantial amounts of steam, hydrogen It is discharged into containment top large space, thus avoids hydrogen in release case compartment 5 inner accumulated, prevent local The containment that hydrogen explosion causes lost efficacy.
Structure of the present invention is not limited to the embodiment described in detailed description of the invention, art technology Personnel draw other embodiment according to technical scheme, also belong to the technology of the present invention Innovation scope.

Claims (4)

1., for reducing a device for nuclear power plant's release case compartment risk, wherein, it is used for placing release Release case compartment (5) of case (6) is located at the middle and lower part of nuclear power plant's containment vessel, described release case (6) upper connection has pressure relief pipeline (10), and pressure relief pipeline (10) passes through relief valve (9) and manostat (8) being connected, described release case (6) top is also equipped with release case explosive valve (7), it is characterised in that Described device includes the discharge duct being connected by connecting tube (12) with release case explosive valve (7) top (2), described discharge duct (2) extends to the upper space in containment vessel, and described aerofluxus The air vent of pipeline (2) is positioned at containment vessel upper space and away from containment wall.
A kind of device for reducing nuclear power plant's release case compartment risk the most according to claim 1, It is characterized in that, connecting tube (12) bottom is connected with release case explosive valve (7), in connecting tube (12) Portion is connected with discharge duct (2) by adpting flange (1).
A kind of dress for reducing nuclear power plant's release case compartment risk the most according to claim 1 and 2 Put, it is characterised in that the air vent of described discharge duct (2) is provided with cover plate (3).
A kind of device for reducing nuclear power plant's release case compartment risk the most according to claim 1, It is characterized in that, discharge duct (2) is fixed in containment by some pipeline support assemblies (4) On structure wall (11).
CN201610329850.5A 2016-05-18 2016-05-18 A kind of device for reducing nuclear power plant's release case compartment risk Active CN106024076B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201610329850.5A CN106024076B (en) 2016-05-18 2016-05-18 A kind of device for reducing nuclear power plant's release case compartment risk

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201610329850.5A CN106024076B (en) 2016-05-18 2016-05-18 A kind of device for reducing nuclear power plant's release case compartment risk

Publications (2)

Publication Number Publication Date
CN106024076A true CN106024076A (en) 2016-10-12
CN106024076B CN106024076B (en) 2019-11-08

Family

ID=57098376

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201610329850.5A Active CN106024076B (en) 2016-05-18 2016-05-18 A kind of device for reducing nuclear power plant's release case compartment risk

Country Status (1)

Country Link
CN (1) CN106024076B (en)

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4086308A (en) * 1975-02-18 1978-04-25 Siemens Aktiengesellschaft Pressurized relief tank for steam
EP0205900A2 (en) * 1985-06-26 1986-12-30 Westinghouse Electric Corporation Pressure control system for a pressurized water nuclear reactor plant
US4692297A (en) * 1985-01-16 1987-09-08 Westinghouse Electric Corp. Control of nuclear reactor power plant on occurrence of rupture in coolant tubes
CN102169731A (en) * 2011-02-14 2011-08-31 中国核电工程有限公司 Device and method for quickly relieving pressure in primary circuit of pressurized water reactor nuclear power plant
CN103871490A (en) * 2012-12-14 2014-06-18 中国核动力研究设计院 Pressure-relief apparatus applied for pressurized water reactor nuclear power plant pressurizer pressure-relief box
CN103971762A (en) * 2014-05-05 2014-08-06 中广核(北京)仿真技术有限公司 Containment vessel for nuclear power plant

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4086308A (en) * 1975-02-18 1978-04-25 Siemens Aktiengesellschaft Pressurized relief tank for steam
US4692297A (en) * 1985-01-16 1987-09-08 Westinghouse Electric Corp. Control of nuclear reactor power plant on occurrence of rupture in coolant tubes
EP0205900A2 (en) * 1985-06-26 1986-12-30 Westinghouse Electric Corporation Pressure control system for a pressurized water nuclear reactor plant
CN102169731A (en) * 2011-02-14 2011-08-31 中国核电工程有限公司 Device and method for quickly relieving pressure in primary circuit of pressurized water reactor nuclear power plant
CN103871490A (en) * 2012-12-14 2014-06-18 中国核动力研究设计院 Pressure-relief apparatus applied for pressurized water reactor nuclear power plant pressurizer pressure-relief box
CN103971762A (en) * 2014-05-05 2014-08-06 中广核(北京)仿真技术有限公司 Containment vessel for nuclear power plant

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
蒋国元 主编: "《WWER-1000核电厂系统与设备》", 30 September 2009, 北京:原子能出版社 *

Also Published As

Publication number Publication date
CN106024076B (en) 2019-11-08

Similar Documents

Publication Publication Date Title
US9697914B2 (en) Nuclear power plant and passive containment cooling system
CN111128414B (en) Active and passive combined safety system and method for nuclear power plant
KR102580625B1 (en) Passive cooling for cold shutdown
US3459635A (en) Containment pressure reduction system and radioactivity removal system for nuclear reactor installations
CN104412328B (en) Filter for a nuclear reactor containment ventilation system
CN102750993B (en) There is the passive containment accidental depressurization system of gas entrapments function of releasing
US11646123B2 (en) Three-way valve operational to both transfer steam to a decontamination water tank under one accident situation and discharge the steam to atmosphere under a different accident situation
US20130259184A1 (en) Containment vessel and nuclear power plant
JP2009150846A (en) Reactor containment vessel and nuclear power plant using it
CN101783187B (en) Exhaustion method for main system of reactor
CN104272399A (en) A method of refueling a nuclear reactor
CN109243634B (en) Reactor safety system
CN209729520U (en) A kind of passive dump of nuclear power station steam generator and cooling system
CA2991079C (en) Residual heat removal ventilation system for spent fuel dry storage facility of nuclear power plant
CN203366752U (en) Passive pressurized water reactor depressurizing system
KR101224024B1 (en) Passive containment cooling system using passive auxiliary feed-water system and irwst
CN205722809U (en) A kind of spray cooling system for Nuclear Power Station's Exhausted Fuels pond
US20200234836A1 (en) System and method for reducing atmospheric release of radioactive materials caused by severe accident
JP7095101B2 (en) Reactor containment building Spent fuel storage water pool vent with pool filter
CN106024076A (en) Device for reducing risk of pressure relief tank compartment of nuclear power plant
JP2012230032A (en) Cooling device for reactor containment vessel
CN214624451U (en) Passive pressure-suppressing spraying system for nuclear power station
CN115359930A (en) Containment cooling and filtering system of nuclear power plant
US3105028A (en) Apparatus for removing contaminated coolant from reactor system
CN208271569U (en) Naval reactor and its Passive residual heat removal system

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant