CN103871484A - Pressurized water reactor nuclear power plant circuit over-pressure protection and pressure-relief system - Google Patents

Pressurized water reactor nuclear power plant circuit over-pressure protection and pressure-relief system Download PDF

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Publication number
CN103871484A
CN103871484A CN201210536842.XA CN201210536842A CN103871484A CN 103871484 A CN103871484 A CN 103871484A CN 201210536842 A CN201210536842 A CN 201210536842A CN 103871484 A CN103871484 A CN 103871484A
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CN
China
Prior art keywords
valve
pressure
pipeline
nuclear power
power plant
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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.)
Pending
Application number
CN201210536842.XA
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Chinese (zh)
Inventor
王保平
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 CN201210536842.XA priority Critical patent/CN103871484A/en
Priority to PCT/CN2013/089031 priority patent/WO2014090145A1/en
Priority to ARP130104646A priority patent/AR093935A1/en
Publication of CN103871484A publication Critical patent/CN103871484A/en
Priority to ZA2015/05014A priority patent/ZA201505014B/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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • 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
    • 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)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Safety Valves (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The invention relates to the technical field of pressurized water reactor nuclear power plant accident treatment, and specifically discloses a pressurized water reactor nuclear power plant circuit over-pressure protection and pressure-relief system, which comprises a pressurizer, a pressure-relief box pipeline, a pressurizer safety valve, a plurality of pneumatic separation valves and a plurality of electrical separation valves, wherein the pipeline positioned on the pressurizer and connected with the pressure-relief box pipeline is provided with the pressurizer safety valve, the pipeline for connecting the pressurizer and the pressure-relief box pipeline is further provided with three parallel connection branches, the first branch comprises the electrical separation valve A and the pneumatic separation valve A, the electrical separation valve A and the pneumatic separation valve A are connected in series, the second branch comprises the electrical separation valve B and the pneumatic separation valve B, the electrical separation valve B and the pneumatic separation valve B are connected in series, the third branch comprises the electrical separation valve C and the pneumatic separation valve C, and the electrical separation valve C and the pneumatic separation valve C are connected in series. With the pressurized water reactor nuclear power plant circuit over-pressure protection and pressure-relief system, the over-pressure protection and pressure-relief function can be performed under working conditions such as normal operation of nuclear power plants, basis accidents and severe accidents so as to maintain the safe status of the reactor.

Description

PWR nuclear power plant one loop overpressure protection and depressurized system
Technical field
The invention belongs to PWR nuclear power plant accident reply technical field, be specifically related to a kind of PWR nuclear power plant one loop overpressure protection and depressurized system.
Background technology
Advanced pressurized water reactor nuclear power plant needs to consider to arrange the device of " fill-arrange " function of carrying out fast pressure relief under a loop overpressure protection, release, major accident operating mode, Low temperature overpressure protection and system in system at present.And a loop overpressure protection of domestic and international existing PWR nuclear power plant and depressurized system can not meet above-mentioned requirements completely.
Summary of the invention
The object of the present invention is to provide a kind of PWR nuclear power plant one loop overpressure protection and depressurized system; can be in the time that system be normally moved, realize a loop overpressure protection and normal pressure relief, and can be under major accident operating mode; realize the fast pressure relief to a loop, prevent high-voltage fuse heap.
Technical scheme of the present invention is as follows: a kind of PWR nuclear power plant one loop overpressure protection and depressurized system, this system comprises voltage stabilizer, remove release case pipeline, pressurizer safety valve, and some pneumatic isolation valves and electronic isolation valve, wherein, on voltage stabilizer with on the pipeline that goes release case pipeline to be connected, be provided with pressurizer safety valve, and be also provided with three branch roads arranged side by side at voltage stabilizer with on the pipeline that goes release case pipeline to be connected, wherein, the first branch road comprises electronic isolation valve A and the pneumatic isolation valve A of series connection, the second branch road comprises electronic isolation valve B and the pneumatic isolation valve B of series connection, the 3rd branch road comprises electronic isolation valve C and the pneumatic isolation valve C of series connection.
Described pressurizer safety valve comprises two spring-type safety valve for pressure stabilizer A arranged side by side and spring-type safety valve for pressure stabilizer B, and spring-type safety valve for pressure stabilizer A accesses voltage stabilizer with on the pipeline that goes release case pipeline to be connected side by side with spring-type safety valve for pressure stabilizer B.
Described voltage stabilizer with on the pipeline that goes release case pipeline to be connected, be also provided with two fast pressure relief branch roads arranged side by side, wherein, the first fast pressure relief branch road comprises electric gate valve A and electric check valve A, the second fast pressure relief branch road comprises electric gate valve B and electric check valve B, in system normal course of operation, two fast pressure relief branch roads are in closed condition, under major accident operating mode, two fast pressure relief branch roads are opened, and carry out discharge pressure relief.
Remarkable result of the present invention is: a kind of PWR nuclear power plant one loop overpressure protection and depressurized system of the present invention; can normally move in nuclear power plant, carry out under benchmark accident and major accident operating mode the function of its overpressure protection and release, to maintain the safe condition of reactor.
Brief description of the drawings
Fig. 1 is a kind of PWR nuclear power plant one loop overpressure protection of the present invention and depressurized system schematic diagram;
In figure: 1, voltage stabilizer; 2, remove release case pipeline; 3, spring-type safety valve for pressure stabilizer A; 4, spring-type safety valve for pressure stabilizer B; 5, electronic isolation valve A; 6, pneumatic isolation valve A; 7, electronic isolation valve B; 8, pneumatic isolation valve B; 9, electronic isolation valve C; 10, pneumatic isolation valve C; 11, electric gate valve A; 12, electric check valve A; 13, electric gate valve B; 14, electric check valve B.
Embodiment
Below in conjunction with drawings and the specific embodiments, the present invention is described in further detail.
As shown in Figure 1, a kind of PWR nuclear power plant one loop overpressure protection and depressurized system, comprise voltage stabilizer 1, remove release case pipeline 2, spring-type safety valve for pressure stabilizer A3, spring-type safety valve for pressure stabilizer B4, and some pneumatic isolation valves and electronic isolation valve, wherein, voltage stabilizer 1 is connected with removing release case pipeline 2 with spring-type safety valve for pressure stabilizer B4 by two and the spring-type safety valve for pressure stabilizer A3 that connects, in the time of normal operation, spring-type safety valve for pressure stabilizer A3 and spring-type safety valve for pressure stabilizer B4 are in closed condition, in the time that reactor coolant loop pressure is elevated to the setting valve of spring-type safety valve for pressure stabilizer A3 and spring-type safety valve for pressure stabilizer B4, spring-type safety valve for pressure stabilizer A3 and spring-type safety valve for pressure stabilizer B4 open discharge, after steam is discharged, system pressure reduces, in the time that system pressure reduces to spring-type safety valve for pressure stabilizer A3 and spring-type safety valve for pressure stabilizer B4 closing presure, the spring-type safety valve for pressure stabilizer A3 and the spring-type safety valve for pressure stabilizer B4 that are connected with voltage stabilizer 1 close automatically.Voltage stabilizer 1 is connected with removing release case pipeline 2 with pneumatic isolation valve by several electronic isolation valves, realize " fill-arrange " function of release, Low temperature overpressure protection and a circuit system to a circuit system, wherein, voltage stabilizer 1 is connected with removing release case pipeline 2 by three branch roads arranged side by side, wherein, the first branch road comprises electronic isolation valve A5 and the pneumatic isolation valve A6 of series connection, the second branch road comprises electronic isolation valve B7 and the pneumatic isolation valve B8 of series connection, and the 3rd branch road comprises electronic isolation valve C9 and the pneumatic isolation valve C10 of series connection; What connected in each pneumatic isolation valve upstream often drives electronic isolation valve, when after each pneumatic isolation valve is opened, pressure reaches and closes definite value, if when pneumatic isolation valve can not cut out, can be by closing electronic isolation valve, to prevent that reactor coolant loop pressure from continuing to decline; In the time that system is normally moved, pneumatic isolation valve is in closed condition, be elevated to the setting valve of pneumatic isolation valve once the pressure of system, automatically open pneumatic isolation valve and realize the release in a loop, in the time that system pressure reduces the closing presure setting valve to pneumatic isolation valve, pneumatic isolation valve cuts out automatically.Two fast pressure relief branch roads arranged side by side are also installed on voltage stabilizer 1, and wherein, the first fast pressure relief branch road comprises electric gate valve A11 and electric check valve A12, and the second fast pressure relief branch road comprises electric gate valve B13 and electric check valve B14; In system normal course of operation, two fast pressure relief branch roads are in closed condition, and under major accident operating mode, two fast pressure relief branch roads are opened, and carry out discharge pressure relief.

Claims (3)

1. PWR nuclear power plant one loop overpressure protection and a depressurized system, it is characterized in that: this system comprises voltage stabilizer (1), remove release case pipeline (2), pressurizer safety valve, and some pneumatic isolation valves and electronic isolation valve, wherein, above be provided with pressurizer safety valve with on the pipeline that goes release case pipeline (2) to be connected at voltage stabilizer (1), and be also provided with three branch roads arranged side by side at voltage stabilizer (1) with on the pipeline that goes release case pipeline (2) to be connected, wherein, the first branch road comprises the electronic isolation valve A(5 of series connection) and pneumatic isolation valve A(6), the second branch road comprises the electronic isolation valve B(7 of series connection) and pneumatic isolation valve B(8), the 3rd branch road comprises the electronic isolation valve C(9 of series connection) and pneumatic isolation valve C(10).
2. a kind of PWR nuclear power plant one loop overpressure protection and depressurized system according to claim 1; it is characterized in that: described pressurizer safety valve comprises two spring-type safety valve for pressure stabilizer A(3 arranged side by side) and spring-type safety valve for pressure stabilizer B(4), spring-type safety valve for pressure stabilizer A(3) with spring-type safety valve for pressure stabilizer B(4) access side by side voltage stabilizer (1) with on the pipeline that goes release case pipeline (2) to be connected.
3. a kind of PWR nuclear power plant one loop overpressure protection and depressurized system according to claim 1, it is characterized in that: described voltage stabilizer (1) with on the pipeline that goes release case pipeline (2) to be connected, be also provided with two fast pressure relief branch roads arranged side by side, wherein, the first fast pressure relief branch road comprises electric gate valve A(11) and electric check valve A(12), the second fast pressure relief branch road comprises electric gate valve B(13) and electric check valve B(14), in system normal course of operation, two fast pressure relief branch roads are in closed condition, under major accident operating mode, two fast pressure relief branch roads are opened, carry out discharge pressure relief.
CN201210536842.XA 2012-12-13 2012-12-13 Pressurized water reactor nuclear power plant circuit over-pressure protection and pressure-relief system Pending CN103871484A (en)

Priority Applications (4)

Application Number Priority Date Filing Date Title
CN201210536842.XA CN103871484A (en) 2012-12-13 2012-12-13 Pressurized water reactor nuclear power plant circuit over-pressure protection and pressure-relief system
PCT/CN2013/089031 WO2014090145A1 (en) 2012-12-13 2013-12-11 Circuit over-voltage protection and voltage relief system of pressurized water reactor nuclear power plant
ARP130104646A AR093935A1 (en) 2012-12-13 2013-12-12 PRESSURE PROTECTION AND PRESSURE DISCHARGE DEVICE OF A CIRCUIT OF A NUCLEAR POWER PLANT WITH PRESSURE WATER REACTOR
ZA2015/05014A ZA201505014B (en) 2012-12-13 2015-07-13 Primary circuit overpressure protection and pressure relief system of pressurized water reactor nuclear power plant

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201210536842.XA CN103871484A (en) 2012-12-13 2012-12-13 Pressurized water reactor nuclear power plant circuit over-pressure protection and pressure-relief system

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CN103871484A true CN103871484A (en) 2014-06-18

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AR (1) AR093935A1 (en)
WO (1) WO2014090145A1 (en)
ZA (1) ZA201505014B (en)

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CN109018287A (en) * 2018-08-01 2018-12-18 中国船舶科学研究中心（中国船舶重工集团公司第七0二研究所） Voltage-stablizer depressurized system for deep-sea nuclear power underwater platform
CN109243633A (en) * 2018-08-13 2019-01-18 中国核电工程有限公司 A kind of nuclear power plant's automation fill-drain syctem
CN110136852A (en) * 2019-04-30 2019-08-16 中广核核电运营有限公司 A kind of one loop of nuclear power station water pressure test overpressure protection system
CN111524623A (en) * 2020-04-30 2020-08-11 中国核动力研究设计院 Constant value and arrangement method for safety valve of voltage stabilizer
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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CN106409360A (en) * 2016-09-27 2017-02-15 中广核研究院有限公司 Method used for achieving nuclear power plant overpressure protection functions
CN112071451B (en) * 2020-09-15 2022-11-01 哈尔滨工程大学 Multifunctional double-layer concrete containment system of pressurized water reactor
CN112163298B (en) * 2020-09-30 2022-02-11 中国核动力研究设计院 Method, equipment and storage medium for analyzing internal environment condition of serious accident pressure relief valve
CN114440206B (en) * 2022-02-10 2023-06-02 华能山东石岛湾核电有限公司 Reverse pressure-bearing protection system of high-temperature gas cooled reactor steam generator

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Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109018287A (en) * 2018-08-01 2018-12-18 中国船舶科学研究中心（中国船舶重工集团公司第七0二研究所） Voltage-stablizer depressurized system for deep-sea nuclear power underwater platform
CN109243633A (en) * 2018-08-13 2019-01-18 中国核电工程有限公司 A kind of nuclear power plant's automation fill-drain syctem
CN109243633B (en) * 2018-08-13 2023-01-17 中国核电工程有限公司 Automatic charging and discharging system of nuclear power plant
CN110136852A (en) * 2019-04-30 2019-08-16 中广核核电运营有限公司 A kind of one loop of nuclear power station water pressure test overpressure protection system
CN111524623A (en) * 2020-04-30 2020-08-11 中国核动力研究设计院 Constant value and arrangement method for safety valve of voltage stabilizer
CN111524623B (en) * 2020-04-30 2022-02-22 中国核动力研究设计院 Constant value and arrangement method for safety valve of voltage stabilizer
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
AR093935A1 (en) 2015-07-01
ZA201505014B (en) 2016-10-26
WO2014090145A1 (en) 2014-06-19

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Application publication date: 20140618