WO2014090106A1 - 一种核电站高压安全注射*** - Google Patents

一种核电站高压安全注射*** 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
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WIPO (PCT)
Prior art keywords
injection
boric acid
reactor
pipeline
pipe section
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PCT/CN2013/088601
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English (en)
French (fr)
Inventor
任云
赖建永
Original Assignee
中国核动力研究设计院
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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/zh
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. .

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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

一种核电站高压安全注射***，配置在反应堆一回路***的若干环路（5）上，包括至少一个硼酸注入单元（15）和至少一个冷却剂注入单元（16）；硼酸注入单元（15）包括浓硼酸注入箱（8）、一端与浓硼酸注入箱（8）连接的浓硼酸注入管路（7），浓硼酸注入管路（7）的另一端穿入安全壳（11）连接到反应堆一回路***的一个环路（5）的冷管段（501）；冷却剂注入单元（16）包括一个水源（14）、与水源（14）连接的冷却剂注入管路（6）；冷却剂注入管路（6）包括并联的冷管段注入管路（9）和热管段注入管路（10）；冷管段注入管路（9）穿入安全壳（11）并连接到反应堆一回路***的一个环路（5）的冷管段（501）上；热管段注入管路（10）穿入安全壳（11）并连接到反应堆一回路的一个环路（5）的热管段（502）上。该注射***的多条管线之间互不干扰，便于流量调节，具有较高的安全性。

Description

一种核电站高压安全注射***
技术领域
本发明涉及压水堆核电站领域， 具体涉及一种用于压水堆核电站的高压 安全注射***。
背景技术
在压水堆核电站中， 安全注射***在发生主冷却剂管道或主蒸汽管道破 裂事故时， 执行堆芯的应急冷却功能， 是重要的专设安全设施之一。 在以往 的设计中， 高压安注***利用化学和容积控制***三台上充泵的其中两台作 为安注泵。每台安注泵的注入流量都通过一个母管汇总后再向各个环路的冷、 热段分配， 这样的设计在某一条注入管线出现故障时， 将会影响其他注入管 线的流量。 高压安注***中设置 1台浓硼酸注入箱， 仅有一条注入管线通过 浓硼酸注入箱， 将浓硼酸溶液注入一回路， 维持堆芯在次临界状态。 如果这 条管线故障， 该功能无法实现， 安全注射***的应急冷却能力降低。
发明内容
本发明的要解决的技术问题是提供一种核电站安全注射***， 其能够独 立地向反应堆一回路注入冷却水， 提高***运行的可靠性， 强化安全注射系 统执行堆芯应急冷却的能力； 并通过单独设置的浓硼酸注入系列在非安全注 射***动作的工况下， 将硼酸溶液注入堆芯， 提供足够的负反应性以实现停 堆。
为了解决上述技术问题， 本发明的技术方案为， 一种核电站高压安全注 射***， 其配置在反应堆一回路***的若干个环路上， 包括至少一个硼酸注 入单元和至少一个冷却剂注入单元；
所述硼酸注入单元包括浓硼酸注入箱、 一端与所述浓硼酸注入箱的连接 的浓硼酸注入管路， 所述浓硼酸注入管路的另一端穿入安全壳连接到反应堆 一回路***的一个环路的冷管段；
所述冷却剂注入单元包括一个水源、与所述水源连接的冷却剂注入管路； 所述冷却剂注入管路包括并联的冷管段注入管路和热管段注入管路； 所述冷 管段注入管路穿入安全壳并连接到反应堆一回路***的一个环路的冷管段 上； 所述热管段注入管路穿入安全壳并连接到反应堆一回路的一个环路的热 管段上。
所述水源可以是安全壳内换料水箱。
所述浓硼酸注入管路上设置有硼酸注入泵； 所述冷却剂注入管路上设置 有高压安注泵。
所述反应堆一回路***包括 3个环路。
所述 3个环路配置有 4个冷却剂注入单元， 其中， 2个冷却剂注入单元 独立地连接在所述反应堆 3个环路中的第一个环路和第二个环路上； 另外 2 个冷却剂注入单元的冷管段注入管路一并连接到所述反应堆 3个环路中的第 三个环路上的冷管段， 所述另外 2个冷却剂注入单元的热管段注入管路一并 连接到所述反应堆 3个环路中的第三个环路上的热管段。
反应堆的 3个环路配置有 2个硼酸注入单元， 所述 3个环路的冷管段通 过一根母管联通； 所述 2个硼酸注入单元的浓硼酸注入管路均连接到所述母 管上； 所述 2个硼酸注入单元的浓硼酸注入管路通过一根连通管路联通， 所 述联通管路上设置有隔离闽。 本发明的有益效果：
( 1 )多条高压安注管线，分别向一回路***的多个环路的冷、热段注入， 多条管线之间互不干扰， 便于流量调节；
(2) 由独立的浓硼酸注入***在安注信号发出后向一回路注入浓硼酸， 该功能不依赖于高压安注泵及相关注入管线的运行；
(3 )在发出停堆信号后， 而控制棒又未能下插导致不能停堆时， 自动启 动硼酸注入泵， 将两台硼酸注入箱内的高浓度硼水注入堆芯从而引入足够的 负反应性以实现停堆。
附图说明
图 1为核电站反应堆一回路***中一个环路的示意图；
图 2为本发明一种核电站高压安全注射***的示意图；
图 3 为本发明一种核电站高压安全注射***的应用到三环路反应堆的局 部示意图 A;
图 4为本发明一种核电站高压安全注射***的应用到三环路反应堆的局 部示意图 B;
图 5 为本发明一种核电站高压安全注射***的应用到三环路反应堆的局 部示意图 C;
图中： 1-反应堆堆芯， 2-压力容器， 3-蒸汽发生器， 4-泵， 5-环路， 6-冷 却剂注入管路， 7-浓硼酸注入管路， 8-浓硼酸注入箱， 9-冷管段注入管路， 10- 热管段注入管路， 11-安全壳， 12-硼酸注入泵， 13-高压安注泵， 14-水源， 15- 硼酸注入单元， 16-冷却剂注入单元， 17-隔离闽， 18-连通管路， 19-母管。
具体实施方式 以下结合附图和实施例对本发明做进一歩描述。
核电站反应堆包括一回路***， 所述一回路***包括 3个环路 5， 图 1 中表示出其中一个环路 5;每个环路均包括热管段 502和冷管段 501 ;冷却剂 通过泵 4由冷管段 501进入压力容器 2并从堆芯 1吸取热量， 吸取热量后的 冷却剂离开压力容器 2由热管段 502经过蒸汽发生器 3释放热量， 释放热量 后的冷却剂回到冷管段 501进而再次进入压力容器 2从而实现循环；
如图 2所示， 本发明一种核电站高压安全注射***， 包括至少一个硼酸 注入单元 15和至少一个冷却剂注入单元 16;
所述硼酸注入单元 15包括浓硼酸注入箱 8、 一端与所述浓硼酸注入箱 8 的底部连接的浓硼酸注入管路 7， 所述浓硼酸注入管路 7的另一端通过贯穿 件穿入安全壳 11连接到反应堆一回路***的一个环路 5的冷管段 501 ;所述 浓硼酸注入管路 7上设置有硼酸注入泵 12;
所述冷却剂注入单元 16包括一个水源 14、与所述水源 14连接的冷却剂 注入管路 6; 所述冷却剂注入管路 6包括并联的冷管段注入管路 9和热管段 注入管路 10; 所述冷管段注入管路 9通过贯穿件穿入安全壳 11并连接到反 应堆一回路的一个环路 5的冷管段 501上;所述热管段注入管路 10通过贯穿 件穿入安全壳 11并连接到反应堆一回路的一个环路 5的热管段 502上；所述 冷却剂注入管路 6上设置有高压安注泵 13 ;所述水源 14可以是安全壳 11内 换料水箱；
如图 3至图 4所示，反应堆的 3个环路 5配置有 4个冷却剂注入单元 16， 其中， 2个冷却剂注入单元 16独立地连接在所述反应堆 3个环路 5中的第一 个和第二个上；另外 2个冷却剂注入单元 16的冷管段注入管路 9一并连接到 所述反应堆 3个环路 5中的第三个上的冷管段 501， 所述另外 2个冷却剂注 入单元 16的热管段注入管路 10—并连接到所述反应堆 3个环路 5中的第三 个上的热管段 502。
如图 5所示， 反应堆的 3个环路 5配置有 2个硼酸注入单元 15， 所述 3 个环路 5的冷管段 501通过一根母管 19联通； 所述 2个硼酸注入单元 15的 浓硼酸注入管路 7均连接到所述母管 19上； 所述 2个硼酸注入单元 15的浓 硼酸注入管路 7上的位于高压安注泵 13与浓硼酸箱 8之间的管路段通过一根 连通管路 18联通， 所述联通管路 18上设置有隔离闽 17。
具体工作工程：
( 1 ) 安全注射过程
一经接收到安注信号就立即执行以下动作：
A) 启动 4个冷却剂注入单元 16上的 4台高压安注泵；
B) 启动两台硼酸注入泵 A和 B;
在安注阶段， 反应堆冷却剂压力迅速下降， 将含硼水注入一回路***的 一个环路 5的冷管段 501并进入反应堆堆芯。
高压安注泵 13以及硼酸注入泵 12的投入使反应堆压力容器再充水并再 淹没反应堆堆芯。
冷管段 501和热管段 502同时注入保证了堆芯的硼浓度低于其溶解度限 值。
在长期安注阶段， 安全注射***仍保持向冷热管段同时注入的配置， 直 到：
A) 完成堆芯冷却；
B) 环境条件 （压力、 温度和放射性水平） 允许进入安全壳。
(2) 浓硼酸注入停堆 在需要停堆而控制棒又发生故障时， 硼酸注入分***作为第二套停堆使 用。 当反应堆保护***发出停堆信号后， 而控制棒又未能下插导致不能停堆 时， 根据停堆信号以及功率量程中子注量率信号的逻辑处理结果， 自动启动 硼酸注入泵 12，将两台硼酸注入箱 8内的高浓度硼水注入堆芯从而引入足够 的负反应性以实现停堆。若其中一个硼酸注入单元 15故障，可以打开连通管 线 18上的隔离闽 17，利用完好的硼酸注入单元 15将高浓度硼酸溶液注入一 回路***的 3个环路的冷管段 501， 实现停堆功能。

Claims

& 禾 J 要
1、 一种核电站高压安全注射***， 其配置在反应堆一回路***的若干 个环路上， 其特征在于： 包括至少一个硼酸注入单元和至少一个冷却剂注入 单元；
所述硼酸注入单元包括浓硼酸注入箱、 一端与所述浓硼酸注入箱的连接 的浓硼酸注入管路， 所述浓硼酸注入管路的另一端穿入安全壳连接到反应堆 一回路***的一个环路的冷管段；
所述冷却剂注入单元包括一个水源、与所述水源连接的冷却剂注入管路； 所述冷却剂注入管路包括并联的冷管段注入管路和热管段注入管路； 所述冷 管段注入管路穿入安全壳并连接到反应堆一回路***的一个环路的冷管段 上； 所述热管段注入管路穿入安全壳并连接到反应堆一回路的一个环路的热 管段上。
2、按照权利要求 1所述的高压安全注射***， 其特征在于： 所述水源可 以是安全壳内换料水箱。
3、 按照权利要求 1所述的高压安全注射***， 其特征在于： 所述浓硼 酸注入管路上设置有硼酸注入泵;所述冷却剂注入管路上设置有高压安注泵。
4、按照权利要求 1所述的高压安全注射***， 其特征在于： 所述反应堆 一回路***包括 3个环路。
5、按照权利要求 4所述的高压安全注射***， 其特征在于： 所述 3个环 路配置有 4个冷却剂注入单元， 其中， 2个冷却剂注入单元独立地连接在所 述反应堆 3个环路中的第一个环路和第二个环路上； 另外 2个冷却剂注入单 元的冷管段注入管路一并连接到所述反应堆 3个环路中的第三个环路上的冷 管段， 所述另外 2个冷却剂注入单元的热管段注入管路一并连接到所述反应 堆 3个环路中的第三个环路上的热管段。
6、 按照权利要求 4所述的高压安全注射***， 其特征在于： 反应堆的 3 个环路配置有 2个硼酸注入单元，所述 3个环路的冷管段通过一根母管联通; 所述 2个硼酸注入单元的浓硼酸注入管路均连接到所述母管上； 所述 2个硼 酸注入单元的浓硼酸注入管路通过一根连通管路联通， 所述联通管路上设置 有隔离闽。
PCT/CN2013/088601 2012-12-11 2013-12-05 一种核电站高压安全注射*** WO2014090106A1 (zh)

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