CN103871504A - Pressurized water reactor nuclear power plant circuit accident gas exhaust system - Google Patents

Pressurized water reactor nuclear power plant circuit accident gas exhaust system Download PDF

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Publication number
CN103871504A
CN103871504A CN201210536706.0A CN201210536706A CN103871504A CN 103871504 A CN103871504 A CN 103871504A CN 201210536706 A CN201210536706 A CN 201210536706A CN 103871504 A CN103871504 A CN 103871504A
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CN
China
Prior art keywords
accident
series
power plant
nuclear power
valve
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.)
Pending
Application number
CN201210536706.0A
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Chinese (zh)
Inventor
张玉龙
任云
赖建永
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Nuclear Power Institute of China
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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 CN201210536706.0A priority Critical patent/CN103871504A/en
Priority to PCT/CN2013/089027 priority patent/WO2014090142A1/en
Priority to ARP130104645A priority patent/AR093934A1/en
Publication of CN103871504A publication Critical patent/CN103871504A/en
Priority to ZA2015/04983A priority patent/ZA201504983B/en
Pending legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/004—Pressure suppression
    • 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

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  • 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 belongs to a pressurized water reactor nuclear power plant accident treatment, and particularly to a pressurized water reactor nuclear power plant circuit accident gas exhaust system, which comprises an accident gas exhaust valve connected between a reactor pressure vessel and a normal gas exhaust valve, wherein the accident gas exhaust valve is divided into two series, is led out from the top of the reactor pressure vessel, passes through two normally closed series connected in parallel, is connected into a pressurizer safety valve exhaust pipeline in a parallel manner, and enters a pressure-relief box, wherein the first normally closed electromagnetic valve and the second normally closed electromagnetic valve form the series A, and the third normally closed electromagnetic valve and the fourth normally closed electromagnetic valve form the series B. The pressurized water reactor nuclear power plant circuit accident gas exhaust system has the following advantage that: the system adopts the electromagnetic valves, has characteristics of stable and reliable performance and quick action, and can be provided for effectively alleviating the severe accident consequence and ensuring the integrity of the reactor pressure vessel under the severe accident.

Description

A kind of PWR nuclear power plant one loop accident exhaust system
Technical field
The invention belongs to a kind of accident answering system of PWR nuclear power plant, be specifically related to a kind of PWR nuclear power plant one loop accident exhaust system.
Background technology
One loop accident exhaust is a kind of severe accident relieving measure.Under accident conditions, accident exhaust system puts into operation, discharges the non-condensable gas that reactor pressure vessel top is gathered, thereby prevents the impact that these not concretive gas conduct heat on reactor core, guarantee to only have unique carbonated drink interface in reactor coolant loop, alleviate damage sequence.
Domestic two generations added nuclear power station in the past only normal exhaust system, only power station start-up course or reload forward and backward, manually to reactor coolant loop exhaust, to system is carried out to the operation of relevant water-filling.Under accident conditions, cannot discharge incoagulable gas of reactor pressure vessel the inside, affect the heat transfer of reactor core.
Summary of the invention
The object of this invention is to provide a kind of PWR nuclear power plant one loop accident exhaust system, under accident conditions, in reactor pressure vessel, can produce a large amount of incoagulability gas, these gases can accumulate in reactor pressure vessel top, in the time that needs are discharged these incoagulability gases, by operator according to corresponding signal and malfunction protocol at the manually opened accident vent valve of main control room, discharge the non-condensable gas that reactor pressure vessel top is gathered, thereby prevent the impact of these not concretive gas on a kind of PWR nuclear power plant one loop accident method for exhausting of reactor core, guarantee to only have unique carbonated drink interface in reactor coolant loop, alleviate damage sequence.
The present invention is achieved in that a kind of PWR nuclear power plant one loop accident exhaust system, and it comprises the accident vent valve being connected between reactor pressure vessel and normal exhaust valve.
Described accident vent valve is divided into two series, from reactor pressure vessel Base top contact, through two normal pass series in parallel, first normal solenoid valve and second normal solenoid valve series A in series that closes of closing, the 3rd normal solenoid valve and the 4th the normal solenoid valve serial B in series that closes of closing, access pressurizer safety valve bleeder line in parallel enters release case.
Advantage of the present invention is that this system is taked solenoid valve, stable and reliable for performance, is swift in motion, and can effectively alleviate major accident consequence, guarantees the integrality of reactor pressure vessel under major accident.
Accompanying drawing explanation
Fig. 1 is a kind of PWR nuclear power plant one loop accident exhaust system schematic diagram provided by the present invention.
In figure, 1 reactor pressure vessel, 2 normal exhaust valves, 3 accident vent valves, 4 nuclear island exhaust and draining systems, 5 release casees, 6 first normal solenoid valves that close, 7 second normal solenoid valves that close, 8 the 3rd normal solenoid valves that close, 9 the 4th normal solenoid valves that close.
Embodiment
Below in conjunction with drawings and Examples, the present invention is described in detail:
" PWR nuclear power plant one loop accident exhaust system ", in the time having an accident, by unlatching accident vent valve, discharges reactor pressure vessel by the incoagulability gas that accumulates in reactor pressure vessel top, alleviates damage sequence.
A kind of PWR nuclear power plant one loop accident exhaust system, it comprises by pipeline and is connected to the accident vent valve 3 between reactor pressure vessel 1 and normal exhaust valve 2, wherein accident vent valve 3 is divided into two series, from reactor pressure vessel Base top contact, through two normal pass series in parallel, it is first normal solenoid valve 6 and second normal solenoid valve 7 series A in series that closes of closing, the 3rd normal solenoid valve 8 and the 4th the normal solenoid valve 9 serial B in series that closes of closing, access pressurizer safety valve bleeder line in parallel, finally enters release case 5 afterwards.
Accident vent valve: when normal reactor operation, this valve closing, is the isolation valve on a border, loop; When accident, open this valve, discharge the non-condensable gas at reactor pressure vessel top.
In the time that unit normally moves, accident exhaust system is for subsequent use, and accident vent valve is in closed condition.Under accident conditions, in reactor pressure vessel, can produce a large amount of incoagulability gas, these gases can accumulate in reactor pressure vessel top, affect the heat transfer of reactor core.
In the time that needs are discharged these incoagulability gases, by operator according to corresponding signal and malfunction protocol at manually opened two the serial accident vent valves of main control room, the incoagulability gas that accumulates in reactor pressure vessel top is discharged to reactor pressure vessel, alleviate damage sequence.

Claims (2)

1. a PWR nuclear power plant one loop accident exhaust system, is characterized in that: it comprises the accident vent valve (3) being connected between reactor pressure vessel (1) and normal exhaust valve (2).
2. a kind of PWR nuclear power plant one loop accident exhaust system as claimed in claim 1, it is characterized in that: described accident vent valve (3) is divided into two series, from reactor pressure vessel Base top contact, through two normal pass series in parallel, first normal solenoid valve (6) and second normal solenoid valve (7) series A in series that closes of closing, the 3rd normal solenoid valve (8) and the 4th normal solenoid valve (9) the serial B in series that closes of closing, access pressurizer safety valve bleeder line in parallel enters release case (5).
CN201210536706.0A 2012-12-13 2012-12-13 Pressurized water reactor nuclear power plant circuit accident gas exhaust system Pending CN103871504A (en)

Priority Applications (4)

Application Number Priority Date Filing Date Title
CN201210536706.0A CN103871504A (en) 2012-12-13 2012-12-13 Pressurized water reactor nuclear power plant circuit accident gas exhaust system
PCT/CN2013/089027 WO2014090142A1 (en) 2012-12-13 2013-12-11 Circuit accident exhaust system of pressurized water reactor nuclear power plant
ARP130104645A AR093934A1 (en) 2012-12-13 2013-12-12 GAS EXHAUST DEVICE FOR ACCIDENT OF A RETURN CIRCUIT OF THE NUCLEAR CENTER OF THE PRESSURE WATER REACTOR
ZA2015/04983A ZA201504983B (en) 2012-12-13 2015-07-10 Primary circuit accident exhaust system of pressurized water reactor nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201210536706.0A CN103871504A (en) 2012-12-13 2012-12-13 Pressurized water reactor nuclear power plant circuit accident gas exhaust system

Publications (1)

Publication Number Publication Date
CN103871504A true CN103871504A (en) 2014-06-18

Family

ID=50909943

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201210536706.0A Pending CN103871504A (en) 2012-12-13 2012-12-13 Pressurized water reactor nuclear power plant circuit accident gas exhaust system

Country Status (4)

Country Link
CN (1) CN103871504A (en)
AR (1) AR093934A1 (en)
WO (1) WO2014090142A1 (en)
ZA (1) ZA201504983B (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112908500A (en) * 2021-01-14 2021-06-04 中广核研究院有限公司 Volume control method for non-condensable gas at top of pressure container
CN114999693A (en) * 2022-06-01 2022-09-02 中国核动力研究设计院 Pressure relief protection system for preventing non-condensable gas from entering reactor core of compressed gas pressure stabilizing reactor

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4873050A (en) * 1987-03-23 1989-10-10 Siemens Aktiengesellschaft Method and apparatus for pressure relief of a nuclear power plant
CN1050460A (en) * 1989-09-19 1991-04-03 三菱重工业株式会社 Core decay heat export system in the pressurized water reactor
WO2005040434A2 (en) * 2003-10-23 2005-05-06 Areva Np Method and device for venting the primary circuit of a nuclear reactor
CN102568621A (en) * 2012-02-27 2012-07-11 清华大学 Primary circuit inclusion body negative pressure exhaust method and system for pebble-bed modular high-temperature gas-cooled reactor
CN203026165U (en) * 2012-12-13 2013-06-26 中国核动力研究设计院 Circuit accident exhaust system of pressurized water reactor nuclear power plant

Family Cites Families (4)

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Publication number Priority date Publication date Assignee Title
JPS5474988A (en) * 1977-11-28 1979-06-15 Toshiba Corp Pressure control apparatus for reactor
US8687759B2 (en) * 2007-11-15 2014-04-01 The State Of Oregon Acting By And Through The State Board Of Higher Education On Behalf Of Oregon State University Internal dry containment vessel for a nuclear reactor
CN202948739U (en) * 2012-10-25 2013-05-22 中国核动力研究设计院 Integrated pressurized water reactor coolant system
CN203397706U (en) * 2013-08-20 2014-01-15 中广核工程有限公司 Nuclear power station pressure vessel accident exhaust system

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4873050A (en) * 1987-03-23 1989-10-10 Siemens Aktiengesellschaft Method and apparatus for pressure relief of a nuclear power plant
CN1050460A (en) * 1989-09-19 1991-04-03 三菱重工业株式会社 Core decay heat export system in the pressurized water reactor
WO2005040434A2 (en) * 2003-10-23 2005-05-06 Areva Np Method and device for venting the primary circuit of a nuclear reactor
CN102568621A (en) * 2012-02-27 2012-07-11 清华大学 Primary circuit inclusion body negative pressure exhaust method and system for pebble-bed modular high-temperature gas-cooled reactor
CN203026165U (en) * 2012-12-13 2013-06-26 中国核动力研究设计院 Circuit accident exhaust system of pressurized water reactor nuclear power plant

Non-Patent Citations (3)

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Title
中国核工业集团公司: "CNP1000核电厂工程技术方案", 《现代电力》 *
中国核工业集团公司: "CNP1000核电厂工程技术方案", 《现代电力》, vol. 23, no. 5, 10 October 2006 (2006-10-10) *
陈小萌: "田湾核电站严重事故缓解系统简介", 《中国核科学技术进展报告（第二卷）》 *

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN112908500A (en) * 2021-01-14 2021-06-04 中广核研究院有限公司 Volume control method for non-condensable gas at top of pressure container
CN112908500B (en) * 2021-01-14 2024-05-10 中广核研究院有限公司 Volume control method for non-condensable gas at top of pressure vessel
CN114999693A (en) * 2022-06-01 2022-09-02 中国核动力研究设计院 Pressure relief protection system for preventing non-condensable gas from entering reactor core of compressed gas pressure stabilizing reactor

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Publication number Publication date
AR093934A1 (en) 2015-07-01
WO2014090142A1 (en) 2014-06-19
ZA201504983B (en) 2016-10-26

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Application publication date: 20140618