WO2014090106A1 - Système d'injection de sûreté à haute pression pour centrales nucléaires - Google Patents

Système d'injection de sûreté à haute pression pour centrales nucléaires Download PDF

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Publication number
WO2014090106A1
WO2014090106A1 PCT/CN2013/088601 CN2013088601W WO2014090106A1 WO 2014090106 A1 WO2014090106 A1 WO 2014090106A1 CN 2013088601 W CN2013088601 W CN 2013088601W WO 2014090106 A1 WO2014090106 A1 WO 2014090106A1
Authority
WO
WIPO (PCT)
Prior art keywords
injection
boric acid
reactor
pipeline
pipe section
Prior art date
Application number
PCT/CN2013/088601
Other languages
English (en)
Chinese (zh)
Inventor
任云
赖建永
Original Assignee
中国核动力研究设计院
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 中国核动力研究设计院 filed Critical 中国核动力研究设计院
Priority to GB1512027.2A priority Critical patent/GB2523949B/en
Publication of WO2014090106A1 publication Critical patent/WO2014090106A1/fr
Priority to ZA2015/04982A priority patent/ZA201504982B/en

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Classifications

    • 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
    • G21C9/02—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency
    • G21C9/033—Means for effecting very rapid reduction of the reactivity factor under fault conditions, e.g. reactor fuse; Control elements having arrangements activated in an emergency by an absorbent fluid
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
    • 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

Definitions

  • the invention relates to the field of pressurized water reactor nuclear power plants, and particularly relates to a high pressure safety injection system for a pressurized water reactor nuclear power plant.
  • the safety injection system performs the emergency cooling function of the core in the event of a main coolant pipe or main steam pipe breakage accident, and is one of the important special safety facilities.
  • the high pressure injection system utilized two of the three charge pumps of the chemical and volume control system as an injection pump. The injection flow rate of each injection pump is distributed through a parent tube and then distributed to the cold and hot sections of each loop. Such a design will affect the flow of other injection pipelines when one injection pipeline fails.
  • a concentrated boric acid injection tank is installed in the high-pressure injection system. Only one injection line is injected into the tank through the concentrated boric acid solution, and the concentrated boric acid solution is injected into the primary circuit to maintain the core in a subcritical state. If this line fails, this feature is not possible and the emergency cooling capacity of the safety injection system is reduced.
  • the technical problem to be solved by the present invention is to provide a nuclear power plant safety injection system capable of independently injecting cooling water into a reactor primary circuit, improving the reliability of the system operation, and strengthening the ability of the safety injection system to perform core emergency cooling;
  • the separately set concentrated boric acid injection series injects the boric acid solution into the core under the action of the non-safe injection system to provide sufficient negative reactivity to achieve shutdown.
  • the technical solution of the present invention is a high-voltage safety injection system for a nuclear power plant, which is disposed on several loops of a primary circuit of the reactor, including at least one boric acid injection. Incoming unit and at least one coolant injection unit;
  • the boric acid injection unit comprises a concentrated boric acid injection tank, a concentrated boric acid injection pipeline connected at one end to the concentrated boric acid injection tank, and the other end of the concentrated boric acid injection pipeline penetrates the safety shell and is connected to one of the reactor primary loop systems. Cold pipe section of the loop;
  • the coolant injection unit includes a water source and a coolant injection pipeline connected to the water source;
  • the coolant injection pipeline includes a parallel cold pipe section injection pipeline and a heat pipe section injection pipeline;
  • the cold pipe section injection pipe The road penetrates the containment and is connected to the cold pipe section of a loop of the reactor primary loop system;
  • the heat pipe section injection pipe penetrates the containment vessel and is connected to the heat pipe section of a loop of the reactor primary circuit.
  • the water source may be a refueling water tank in the containment.
  • the concentrated boric acid injection line is provided with a boric acid injection pump; and the coolant injection line is provided with a high pressure injection pump.
  • the reactor primary loop system includes three loops.
  • the three loops are configured with four coolant injection units, wherein two coolant injection units are independently connected to the first loop and the second loop of the three loops of the reactor;
  • the cold pipe section injection line of the coolant injection unit is connected to the cold pipe section on the third of the three loops of the reactor, and the heat pipe sections of the other two coolant injection units are injected together Connected to the heat pipe section on the third of the three loops of the reactor.
  • the three loops of the reactor are provided with two boric acid injection units, and the cold tube sections of the three loops are connected by a single mother tube; the concentrated boric acid injection lines of the two boric acid injection units are connected to the mother tube
  • the concentrated boric acid injection pipeline of the two boric acid injection units is connected through a communication pipeline, and the communication pipeline is provided with an isolation crucible.
  • a plurality of high-pressure injection lines are injected into the cold and hot sections of the multiple loops of the primary loop system, and the multiple pipelines do not interfere with each other, which facilitates flow regulation;
  • Figure 1 is a schematic diagram of a loop in a primary loop system of a nuclear power plant reactor
  • FIG. 2 is a schematic view of a nuclear power plant high pressure safety injection system according to the present invention.
  • Figure 3 is a partial schematic view of a nuclear power plant high pressure safety injection system applied to a three-loop reactor according to the present invention
  • Figure 4 is a partial schematic view of a nuclear power plant high pressure safety injection system applied to a three-loop reactor in accordance with the present invention
  • Figure 5 is a partial schematic view C of a nuclear power plant high-pressure safety injection system applied to a three-loop reactor according to the present invention
  • 1-reactor core 2-pressure vessel, 3- steam generator, 4-pump, 5-loop, 6-coolant injection line, 7-concentrated boric acid injection line, 8-concentrated boric acid injection Box, 9-cold pipe section injection line, 10-heat pipe section injection line, 11-safety shell, 12-boric acid injection pump, 13-high pressure injection pump, 14-water source, 15-boric acid injection unit, 16-coolant Injection unit, 17-isolation 18, 18-connected line, 19-mother tube.
  • the nuclear power plant reactor includes a primary circuit system, and the primary circuit system includes three loops 5, FIG. One of the loops 5 is shown; each loop includes a heat pipe section 502 and a cold pipe section 501; the coolant enters the pressure vessel 2 from the cold pipe section 501 through the pump 4 and extracts heat from the core 1, and the coolant after drawing heat Leaving the pressure vessel 2, the heat pipe section 502 releases heat through the steam generator 3, and the released heat is returned to the cold pipe section 501 to enter the pressure vessel 2 again to achieve circulation;
  • a nuclear power plant high pressure safety injection system of the present invention includes at least one boric acid injection unit 15 and at least one coolant injection unit 16;
  • the boric acid injection unit 15 includes a concentrated boric acid injection tank 8 and a concentrated boric acid injection line 7 connected at one end to the bottom of the concentrated boric acid injection tank 8. The other end of the concentrated boric acid injection line 7 penetrates through the penetration member.
  • the shell 11 is connected to a cold tube section 501 of a loop 5 of the reactor primary loop system; the concentrated boric acid injection line 7 is provided with a boric acid injection pump 12;
  • the coolant injection unit 16 includes a water source 14 and a coolant injection line 6 connected to the water source 14; the coolant injection line 6 includes a parallel cold pipe section injection line 9 and a heat pipe section injection line 10
  • the cold pipe section injection pipe 9 penetrates the safety casing 11 through the penetration member and is connected to the cold pipe section 501 of a loop 5 of the reactor primary circuit; the heat pipe section injection pipe 10 penetrates the safety casing 11 through the penetration member.
  • the coolant injection pipeline 6 is provided with a high pressure injection pump 13;
  • the water source 14 may be a refueling water tank in the safety enclosure 11;
  • three loops 5 of the reactor are arranged with four coolant injection units 16, wherein two coolant injection units 16 are independently connected to the third of the three loops 5 of the reactor.
  • One and the second; the cold pipe section injection line 9 of the other two coolant injection units 16 is connected to the cold pipe section 501 on the third of the three loops 5 of the reactor, the other two The heat pipe section of the coolant injection unit 16 is injected into the pipe 10 - and connected to the third of the three loops 5 of the reactor Upper heat pipe section 502.
  • the three loops 5 of the reactor are provided with two boric acid injection units 15, and the cold tube segments 501 of the three loops 5 are connected by a single mother tube 19; the two boric acid injection units 15
  • the concentrated boric acid injection line 7 is connected to the mother tube 19; the pipeline section between the high pressure injection pump 13 and the concentrated borate tank 8 on the concentrated boric acid injection line 7 of the two boric acid injection units 15 passes A communication line 18 is connected, and the communication line 18 is provided with an isolation crucible 17.
  • the reactor coolant pressure drops rapidly, injecting boron-containing water into the cold section 501 of a loop 5 of the primary loop system and into the reactor core.
  • the input of the high pressure injection pump 13 and the boric acid injection pump 12 refills the reactor pressure vessel and submerges the reactor core.
  • the safety injection system still maintains a simultaneous injection into the hot and cold sections until:
  • the boric acid injection subsystem is used as a second shutdown when the reactor needs to be shut down and the control rod fails.
  • the boric acid injection pump 12 is automatically activated according to the logic of the shutdown signal and the power range neutron fluence rate signal.
  • the high concentration of boron water in the two boric acid injection tanks 8 is injected into the core to introduce sufficient negative reactivity to achieve shutdown.
  • the isolation crucible 17 on the communication line 18 can be opened, and the high-concentration boric acid solution is injected into the cold-circuit section 501 of the three loops of the primary loop system by the intact boric acid injection unit 15 to realize the shutdown function. .

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

L'invention porte sur un système d'injection de sûreté à haute pression pour centrales nucléaires, qui est installé sur de multiples boucles (5) d'un système de boucle d'un réacteur. Le système d'injection de sûreté à haute pression comprend au moins une unité d'injection d'acide borique (15) et au moins une unité d'injection de fluide réfrigérant (16). L'unité d'injection d'acide borique (15) comprend une boîte d'injection d'acide borique concentré (8) et une conduite d'injection d'acide borique concentré (7). Une première extrémité de la conduite d'injection d'acide borique concentré (7) est raccordée à la boîte d'injection d'acide borique concentré (8), et l'autre extrémité de la conduite d'injection d'acide borique concentré (7) pénètre dans un récipient de confinement (11), puis est raccordée à une section de tube froid (501) d'une boucle (5) d'un système de boucle du réacteur. L'unité d'injection de fluide réfrigérant (16) comprend une source d'eau (14) et une conduite d'injection de fluide réfrigérant (6) raccordée à la source d'eau (14). La conduite d'injection de fluide réfrigérant (6) comprend une conduite d'injection de section de tube froid (9) et une conduite d'injection de section de tube chaud (10) qui sont reliées en parallèle ; la conduite d'injection de section de tube froid (9) pénètre dans le récipient de confinement (11), puis est raccordée à une section de tube froid (501) d'une boucle (5) d'un système de boucle du réacteur ; et la conduite d'injection de section de tube froid (10) pénètre dans le récipient de confinement (11), puis est reliée à une section de tube froid (502) d'une boucle (5) d'un système de boucle du réacteur. Les multiples conduites du système d'injection ne sont pas en interférence mutuelle, ce qui facilite ainsi le contrôle de flux ; et le système d'injection possède une haute sécurité.
PCT/CN2013/088601 2012-12-11 2013-12-05 Système d'injection de sûreté à haute pression pour centrales nucléaires WO2014090106A1 (fr)

Priority Applications (2)

Application Number Priority Date Filing Date Title
GB1512027.2A GB2523949B (en) 2012-12-11 2013-12-05 High-pressure safe injection system for nuclear power stations
ZA2015/04982A ZA201504982B (en) 2012-12-11 2015-07-10 High-pressure safe injection system for nuclear power stations

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
CN201210531614.3A CN103871506B (zh) 2012-12-11 2012-12-11 一种核电站高压安全注射系统
CN201210531614.3 2012-12-11

Publications (1)

Publication Number Publication Date
WO2014090106A1 true WO2014090106A1 (fr) 2014-06-19

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PCT/CN2013/088601 WO2014090106A1 (fr) 2012-12-11 2013-12-05 Système d'injection de sûreté à haute pression pour centrales nucléaires

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CN (1) CN103871506B (fr)
AR (1) AR093899A1 (fr)
GB (1) GB2523949B (fr)
WO (1) WO2014090106A1 (fr)
ZA (1) ZA201504982B (fr)

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CN105244062B (zh) * 2014-07-09 2017-07-14 国核华清（北京）核电技术研发中心有限公司 非能动蓄压安注系统和非能动蓄压安注方法
CN104616707B (zh) * 2014-12-30 2017-03-22 中国原子能科学研究院 一种用于研究堆第二停堆系统的注硼系统
CN106887259A (zh) * 2015-12-15 2017-06-23 中国核动力研究设计院 一种核电厂快速安全停堆系统
CN109147967B (zh) * 2017-06-15 2022-08-16 广东核电合营有限公司 一种用于核电站的硼浓度控制装置和方法
CN108091407B (zh) * 2017-11-10 2019-11-15 中广核研究院有限公司 高压安注系统及其安全注入方法
CN109300556A (zh) * 2018-09-19 2019-02-01 中广核研究院有限公司 一种具备安注功能的反应堆稳压系统
CN109473185B (zh) * 2018-11-13 2022-07-29 中国核动力研究设计院 一种自动化学停堆系统的测试装置及其测试方法
CN109859866B (zh) * 2019-03-06 2022-02-22 中国核动力研究设计院 一种缓解主蒸汽管道破裂事故后果的方法
CN110580957B (zh) * 2019-09-19 2021-04-06 中国核动力研究设计院 一种无外加中子源的反应堆装料启动方法
CN111128410B (zh) * 2019-12-31 2022-07-26 中国核动力研究设计院 一种热管反应堆系统及其能量转换方式
CN115237046A (zh) * 2022-07-21 2022-10-25 中国核动力研究设计院 一种安注信号手动禁止方法、装置、终端及可读存储介质

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Also Published As

Publication number Publication date
CN103871506A (zh) 2014-06-18
GB201512027D0 (en) 2015-08-19
CN103871506B (zh) 2016-12-21
GB2523949B (en) 2020-07-01
AR093899A1 (es) 2015-06-24
GB2523949A (en) 2015-09-09
ZA201504982B (en) 2016-12-21
GB2523949A8 (en) 2015-09-16

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