WO2020151588A1 - 一种具有迷宫式流道的池式铅基快堆 - Google Patents

一种具有迷宫式流道的池式铅基快堆 Download PDF

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WO2020151588A1
WO2020151588A1 PCT/CN2020/072687 CN2020072687W WO2020151588A1 WO 2020151588 A1 WO2020151588 A1 WO 2020151588A1 CN 2020072687 W CN2020072687 W CN 2020072687W WO 2020151588 A1 WO2020151588 A1 WO 2020151588A1
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Prior art keywords
pool
cold
reactor
partition
hot
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PCT/CN2020/072687
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English (en)
French (fr)
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陈钊
宋磊
仇若翔
段承杰
崔大伟
张勇
石秀安
林继铭
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中广核研究院有限公司
中国广核集团有限公司
中国广核电力股份有限公司
岭东核电有限公司
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Publication of WO2020151588A1 publication Critical patent/WO2020151588A1/zh

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    • 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
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
    • 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
    • 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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  • the invention relates to the technical field of nuclear reactors, in particular to a pool type lead-based fast reactor with labyrinth flow channels.
  • nuclear power plants can produce high energy output that is unmatched by all other traditional fossil energy sources, and these high energy outputs often require only a small amount of nuclear fuel. This feature of low input and high output has made nuclear energy an important energy component in many countries in the world. However, while nuclear power has extremely high utility value, its possible harm also makes people talk about nuclear discoloration.
  • the prior art discloses a Chinese invention patent with application number 201280077308.5 named as a nuclear reactor with liquid metal coolant.
  • This invention uses a pipe connection between the heat pool and the heat exchanger, but because the pipe is located in the reactor This increases the complexity of the internal components of the stack, and at the same time increases the flow resistance of the primary loop coolant, resulting in higher power requirements for the drive pump.
  • the prior art also discloses a Chinese invention patent with application number 200880117773.0, named as a nuclear reactor with a new concept fuel element, and application number 201510061189.X, named as a main circuit for a pool-type liquid heavy metal cooling reactor
  • the Chinese invention patent of the circulation device but both of the primary loop flow channel designs of the two have the risk that when the heat transfer tube ruptures in the heat exchanger, tiny bubbles or water droplets may enter the reactor core, and it is easy to introduce positive reactivity. Lead to an over-power accident.
  • the inventor proposes a pool-type lead-based fast reactor with labyrinth flow channels, which can not only reduce the complexity of the internal components of the reactor and the flow resistance of the primary circuit coolant, but also avoid the heat transfer tube rupture of the heat exchanger. , The risk of tiny bubbles or water droplets entering the reactor core.
  • the technical problem to be solved by the embodiments of the present invention is to provide a pool type lead-based fast reactor with labyrinth flow channels, which can not only reduce the complexity of the internal components of the reactor and the flow resistance of the primary loop coolant, but also avoid heat exchange.
  • the heat transfer tube of the reactor is ruptured, there is a risk that tiny bubbles or water droplets enter the reactor core.
  • the embodiments of the present invention provide a pool type lead-based fast reactor with labyrinth flow channels, including a reactor vessel, a reactor roof, a lower head, a core mounting member, a core, a control rod, and The driving mechanism, the cold and hot pool partition, the first auxiliary partition, the heat exchanger and the driving pump; among them,
  • the reactor vessel is in the shape of a hollow column, the top end of which is connected with the top cover of the reactor to form a sealed connection, and the bottom end of the reactor vessel is connected to the lower head to form a sealed connection;
  • the stack top cover is provided with a first inlet and a second inlet and outlet for liquid or gas in and out;
  • the core installation member is arranged in the reactor vessel and above the lower head, and the top of the core installation member is provided with an installation position for installing the core;
  • the core is installed on the installation position on the top of the core installation member
  • One end of the control rod and its driving mechanism is located outside the reactor vessel, and the other end passes through the reactor top cover and enters the reactor vessel to be connected to the top of the reactor core;
  • the cold and hot pool partition is arranged in the reactor vessel and sleeved outside the control rod and its driving mechanism. It is in the shape of a hollow cone. The bottom of the cone is connected with the top cover of the reactor to form a sealed connection, The top of the cone is sleeved on the outer wall of the core to form a sealed connection; wherein the cold and hot pool partition separates the reactor vessel into an unconnected hot pool and a cold pool; the hot pool is composed of The reactor core, the cold and hot pool partitions and the reactor top cover are enclosed, and the first coolant and the first inert gas that enter and exit through the first inlet and outlet are contained inside; The remaining cavity space in the reactor vessel excluding the hot pool is formed, and the second coolant and the second inert gas that enter and exit through the second inlet and outlet are contained therein;
  • the first auxiliary partition includes a horizontal partition and a vertical partition formed along the peripheral edges of the horizontal partition and simultaneously extending toward the stack top cover; wherein the middle part of the horizontal partition is sleeved On the outer wall of the cold and hot pool partition and form a sealed connection with the cold and hot pool partition; the vertical partition is arranged toward the cold and hot pool partition and is located between the cold and hot pool partition Reserve a certain distance;
  • each heat exchanger is located outside the reactor vessel, and the other end passes through the heat pool formed by the top cover and the cold and hot pool partition in sequence. Enter the cold pool and be located in the gap reserved between the first auxiliary partition and the cold and hot pool partition;
  • each drive pump There is at least one drive pump, and one end of each drive pump is located outside the reactor vessel, and the other end passes through the top cover of the reactor and enters the cold pool and is located away from the first auxiliary partition One side of the core.
  • each second auxiliary partition is connected to the side wall of the cold and hot pool partition, and the other end extends parallel to the direction of the center axis of the corresponding heat exchanger and is located between the first auxiliary partition and the In the gap reserved between the partitions of the cold and hot pools.
  • the stack top plug is arranged in the hot pool, sleeved on the outer wall of the control rod and its driving mechanism, and is arranged close to the stack top cover.
  • the side wall of the cold and hot pool partition includes a first side wall, a second side wall, and a third side wall that are vertically connected in sequence;
  • the first side wall is vertically connected to the stack top cover, and its end away from the second side wall faces the stack top cover and is connected to the stack top cover to form a sealed connection;
  • the second side wall is parallel to the first side wall, and its end connected to the third side wall is located close to the control rod and its driving mechanism; wherein, each heat exchanger passes through the The second side wall enters the cold pool and is located in the gap reserved between the first auxiliary partition and the cold and hot pool partition;
  • the third side wall is parallel to the first side wall, and its end away from the second side wall faces the core and is connected to the core to form a sealed connection.
  • the horizontal partition of the first auxiliary partition is parallel to the second side wall of the cold and hot pool partition
  • the vertical partition of the first auxiliary partition is parallel to the second side wall of the cold and hot pool partition.
  • the first side wall and the third side wall are parallel.
  • the core mounting member is in the shape of a hollow cone
  • the bottom of the vertebral body is provided with a channel radially penetrating through and connected to the reactor vessel in a loop
  • the top of the vertebral body is provided with an installation position for installing the core.
  • a high-temperature resistant concrete layer arranged between the reactor container and the top cover of the reactor.
  • each heat exchanger is a heat transfer tube.
  • first coolant and the second coolant are both liquid metallic lead or lead-bismuth alloy; the first inert gas and the second inert gas are both argon.
  • the reactor vessel is divided into a hot pool and a cold pool that are not connected to each other through the cold and hot pool partitions, and the first coolant in the hot pool is formed by immersing the two ends of the heat exchanger simultaneously connecting the hot pool and the cold pool Therefore, there is no need to set up pipelines, which not only reduces the complexity of reactor internal components, improves the reliability of reactor operation, but also reduces the flow resistance of the primary loop coolant, thereby reducing the power of driving the pump Claim.
  • the present invention uses the first auxiliary baffle to block the direct sinking of tiny bubbles or water droplets when the heat transfer tube ruptures in the heat exchanger, which increases the time for rupture of tiny bubbles or water droplets, thereby avoiding direct entry of tiny bubbles or water droplets
  • the risk of the reactor core, and the horizontal partition of the first auxiliary partition, in the event of an earthquake or shaking, can slow down the sloshing amplitude of the coolant level, thereby reducing the mechanical impact of the internal components and the main container, and improving the entire The resistance of the reactor device to earthquakes or shaking.
  • Fig. 1 is a plan cross-sectional view of a pool-type lead-based fast reactor with labyrinth flow channels provided by an embodiment of the present invention.
  • FIG. 1 it is a pool type lead-based fast reactor with labyrinth flow channels provided in an embodiment of the present invention, including a reactor vessel 1, a reactor top cover 2, a lower head 3, and a core mounting member 4 , The core 5, the control rod and its driving mechanism 6, the cold and hot pool partition 7, the first auxiliary partition 8, the heat exchanger 9 and the driving pump 10;
  • the reactor vessel 1 is in the shape of a hollow cylinder. Its top end is connected with the top cover 2 to form a sealed connection, and the bottom end is connected to the lower head 3 to form a sealed connection; in one example, the reactor vessel 1 adopts a hollow cylindrical metal container with a top
  • the cover 2 is made of steel and is placed on the top of the reactor vessel 1 to form a sealed connection.
  • the lower head 3 is a hemispherical or elliptical head that forms a sealed connection with the bottom end of the reactor vessel 1, so that the entire reactor vessel 1, reactor The top cover 2 and the lower head 3 form a sealed tank;
  • the top cover 2 is provided with a first inlet 21 and a second inlet 22 for liquid or gas in and out to facilitate the injection of coolant and inert gas into the sealed tank; it should be noted that the first inlet 21 and the second The number of import and export 22 can be designed into multiple according to actual;
  • the core installation member 4 is arranged in the reactor vessel 1 and above the lower head 3, and the top of the core installation member 4 is provided with an installation position for installing the core 5; in one example, the core installation member 4 is made of hollow steel. Cone structure, the bottom of the cone is provided with a channel 41 radially penetrating through and connected to the reactor vessel 1 to form a loop. The top of the cone is provided with a mounting position for installing the core 5, and the core mounting member 4 adopts the above-mentioned hollow cone The structure is favorable for the coolant in the reactor vessel 1 to enter the core mounting member 4 and contact the core 5 to achieve a heat exchange effect;
  • the core 5 is installed on the installation position on the top of the core installation member 4;
  • control rod and its drive mechanism 6 is located outside the reactor vessel 1, and the other end passes through the top cover 2 of the reactor and enters the reactor vessel 1 and is connected to the top of the core 5; it is understandable that the control rod drive mechanism is located in the reactor vessel Outside of 1, the control bank extends into the reactor vessel 1 and is connected to the top of the core 5;
  • the cold and hot pool partition 7 is made of steel, and is arranged in the reactor vessel 1 and sleeved outside the control rod and its driving mechanism 6. It is in the shape of a hollow cone, and the bottom of the cone faces the top cover 2 and is connected to the top of the reactor.
  • the hot and cold pool partition 7 isolates the reactor vessel 1 into mutually disconnected hot pools T1 and the cold pool T2; the hot pool T1 is enclosed by the core 5, the hot and cold pool partition 7 and the top cover 2 of the reactor, and contains the first coolant and the second coolant that enter and exit through the first inlet and outlet 21.
  • the cold pool T2 is formed by the remaining cavity space in the reactor vessel 1 except for the hot pool 11, which contains the second coolant and the second inert gas that enter and exit through the second inlet and outlet 22;
  • the first coolant and the second coolant are both liquid metallic lead or lead-bismuth alloy;
  • the first inert gas and the second inert gas are both argon;
  • the first auxiliary partition 8 is made of steel, and includes a horizontal partition 81 and a vertical partition 82 extending along the peripheral edges of the horizontal partition 81 toward the stack top cover 2; wherein, the middle of the horizontal partition 81
  • the part is sleeved on the outer wall of the hot and cold pool partition 7 and forms a sealed connection with the hot and cold pool partition 7, so as to prevent the second coolant enclosed between the first auxiliary partition 8 and the hot and cold pool partition 7 from being directly
  • the sinker makes contact with the core 2 so as to prevent the danger of the tiny vapor bubbles or water droplets generated in the second coolant enclosed between the first auxiliary partition 8 and the hot and cold pool partition 7 from directly entering the core 2;
  • the straight partition 82 is set toward the cold and hot pool partition 7, and a certain distance is reserved between the cold and hot pool partition 7, which can extend the first auxiliary partition 8 and the cold and hot pool partition 7 2. The time for the tiny bubbles or water droplets generated in the coolant to burst;
  • each heat exchanger 9 is located outside the reactor vessel 1, and the other end passes through the hot pool T1 formed by the top cover 2 and the hot and cold pool partition 7 in turn before entering the cold
  • the pool T2 is located in the gap reserved between the first auxiliary partition 8 and the hot and cold pool partition 7, so that the hot pool T1 can use the heat difference between the two ends of the heat exchanger 9 to realize the flow of the first coolant in the pool, and
  • the heat of the core 5 is taken away and transferred to the cold pool T2 to realize the heat exchange effect of the core 5.
  • the small vapor bubbles or water droplets generated in the second coolant can be It is effectively blocked by the first auxiliary partition 8 and the cold and hot pool partition 7; in one example, there are multiple heat exchangers 9 arranged annularly around the control rods, and they are all heat transfer tubes;
  • each drive pump 10 There is at least one drive pump 10, and one end of each drive pump 10 is located outside the reactor vessel 1, and the other end passes through the top cover 2 into the cold pool T2 and is located at the first auxiliary partition 8 away from the core 5 One side; it is understandable that after the drive pump 10 is started, the circulating flow rate of the second coolant in the cold pool T2 is accelerated to accelerate the heat exchange effect on the core 5; in one example, there are multiple drive pumps 10, each A motor drive mechanism for driving the top of the pump 10 is located outside the reactor vessel 1, and a stirring rod at the bottom is located in the cold pool T2.
  • top, bottom, top and bottom of all components are based on the stack top cover 2, the end facing the stack top cover 2 is the top or top, and the end away from the stack top cover 2 is the bottom. End or bottom.
  • each second auxiliary partition 11 corresponding to each heat exchanger 9; wherein, each second auxiliary partition 11 is made of steel, and one end of the second auxiliary partition 11 is made of steel.
  • the side walls of the pool partition 7 are connected, and the other end extends parallel to the center axis of the corresponding heat exchanger 9 and is located in the gap reserved between the first auxiliary partition 8 and the hot and cold pool partition 7, thereby
  • the second auxiliary partition 11 and the first auxiliary partition 8 are staggered and arranged into a labyrinth-like flow channel.
  • a top plug 12 made of steel; the top plug 12 is arranged in the hot pool T1, and is sleeved on the outer wall of the control rod and its driving mechanism 6, and is close to the top of the stack
  • the cover 2 is provided, and the top plug 12 provides support and a through passage, which can be disassembled during the refueling period to provide a refueling passage.
  • the hot and cold pool partition 7 is a stepped vertebral structure, and its side walls include a first side wall 71, a second side wall 72, and a third side wall 73 that are vertically connected in sequence;
  • the first side wall 71 is vertically connected to the stack top cover 2, and its end away from the second side wall 72 faces the stack top cover 2 and is connected to the stack top cover 2 to form a sealed connection;
  • the second side wall 72 is parallel to the first side wall 71, and its end connected to the third side wall 73 is located close to the control rod and its driving mechanism 6; wherein, each heat exchanger 9 passes through the second side wall 72 enters the cold pool T2 and is located in the gap reserved between the first auxiliary partition 8 and the hot and cold pool partition 7;
  • the third side wall 73 is parallel to the first side wall 71, and its end away from the second side wall 72 faces the core 5 and is connected to the core 5 to form a sealed connection.
  • the cold and hot pool partition 7 adopts a stepped vertebral structure, which facilitates the installation of the heat exchanger 9 and enlarges the heat exchange area of the heat exchanger 9 in the hot pool T1.
  • the horizontal partition 81 of the first auxiliary partition 8 is parallel to the second side wall 72 of the hot and cold pool partition 7, and the vertical partition 82 of the first auxiliary partition 8 is parallel to the hot and cold pool partition.
  • the first side wall 71 and the third side wall 73 of the partition 7 are parallel.
  • the cross section of the channel 41 of the core mounting member 4 is wavy, which is beneficial to speed up the flow rate of the second coolant.
  • it further includes: a high-temperature resistant concrete layer 13 arranged between the reactor vessel 1 and the top cover 2 of the reactor, which is beneficial to avoid evaporation of the liquid coolant in the reactor vessel 1.
  • the reactor vessel is divided into a hot pool and a cold pool that are not connected to each other through the cold and hot pool partitions, and the first coolant in the hot pool is formed by immersing the two ends of the heat exchanger simultaneously connecting the hot pool and the cold pool Therefore, there is no need to set up pipelines, which not only reduces the complexity of reactor internal components, improves the reliability of reactor operation, but also reduces the flow resistance of the primary loop coolant, thereby reducing the power of driving the pump Claim.
  • the present invention uses the first auxiliary baffle to block the direct sinking of tiny bubbles or water droplets when the heat transfer tube ruptures in the heat exchanger, which increases the time for rupture of tiny bubbles or water droplets, thereby avoiding direct entry of tiny bubbles or water droplets
  • the risk of the reactor core, and the horizontal partition of the first auxiliary partition, in the event of an earthquake or shaking, can slow down the sloshing amplitude of the coolant level, thereby reducing the mechanical impact of the internal components and the main container, and improving the entire The resistance of the reactor device to earthquakes or shaking.

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  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
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  • High Energy & Nuclear Physics (AREA)
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Abstract

一种具有迷宫式流道的池式铅基快堆，包括反应堆容器（1）、堆顶盖（2）、下封头（3）、堆芯安装构件（4）、堆芯（5）、控制棒及其驱动机构（6）、冷热池隔板（7）、第一辅助隔板（8）、热交换器（9）及驱动泵（10）；反应堆容器（1）与堆顶盖（2）及下封头（3）分别形成密封连接；堆芯（5）安装于堆芯安装构件（4）的安装位上；控制棒及其驱动机构（6）进入反应堆容器（1）中与堆芯（5）顶部相连；冷热池隔板（7）使反应堆容器（1）隔离成互不连通的热池（T1）和冷池（T2）；第一辅助隔板（8）位于冷热池隔板（7）外侧并与冷热池隔板（7）有一定距离；热交换器（9）穿过热池（T1）进入冷池（T2）中实现热传导；驱动泵（10）进入冷池（T2）实现冷池（T2）中冷却剂循环。具有迷宫式流道的池式铅基快堆不仅能降低堆内构件的复杂性及一回路冷却剂的流动阻力，还能避免热交换器（9）发生传热管破裂时，微小汽泡或水滴进入反应堆堆芯（5）的风险。

Description

一种具有迷宫式流道的池式铅基快堆
本申请要求于2019年1月25日提交中国专利局、申请号为201910072898.6、发明名称为“一种具有迷宫式流道的池式铅基快堆”的中国专利申请的优先权，上述专利的全部内容通过引用结合在本申请中。
技术领域
本发明涉及核反应堆技术领域，尤其涉及一种具有迷宫式流道的池式铅基快堆。
背景技术
核电的使用是人类在能源利用史上的一个重大突破，利用原子核的裂变反应，核电厂能够产生其他所有传统化石能源所无法比拟的高能量输出，并且这些高能量输出往往只需要耗费少量的核燃料。这种低投入高产出的特性，使得核能已经成为世界上许多国家的重要能源组成部分，然而核电在具有极高利用价值的同时，其所可能带来的危害也令人们谈核色变。
在使用核电的过程中，一旦压水堆中反应堆容器温度迅速上升，若不及时冷却并将反应堆容器的热量导出，就可能使安全壳的温度及压力升高，从而引发严重的安全事故，将会对核电厂周边的环境乃至全人类带来及其严重的核污染灾害，因此需要对安全壳进一步设置安全保障措施。
为了解决上述问题，现有技术中公开了申请号为201280077308.5，名称为具有液态金属冷却剂的核反应堆的中国发明专利，该发明在热池与热交换器间采用管道连接，但是因管道位于堆内而增加了堆内构件的复杂性，同时还增加了一回路冷却剂的流动阻力，从而导致对驱动泵的功率要求较高。现有技术中又公开了申请号为200880117773.0，名称为具有新概念燃料元件的核反应堆的中国发明专利以及公开了申请号为201510061189.X，名称为一种用于池式液态重金属冷却反应堆的主回路循环装置的中国发明专利，但是二者的一回路流道设计中都存在热交换器发生传热管破裂时，微小汽泡或水滴有可能进入反应堆堆芯的风险，极易引入正反应性，导致超功率事故发生。
因此，发明人提出一种具有迷宫式流道的池式铅基快堆，不仅能降低堆内构件的复杂性及一回路冷却剂的流动阻力，还能避免热交换器发生传热管破裂时，微小汽泡或水滴进入反应堆堆芯的风险。
发明内容
本发明实施例所要解决的技术问题在于，提供一种具有迷宫式流道的池式铅基快堆，不仅能降低堆内构件的复杂性及一回路冷却剂的流动阻力，还能避免热交换器发生传热管破裂时，微小汽泡或水滴进入反应堆堆芯的风险。
为了解决上述技术问题，本发明实施例提供了一种具有迷宫式流道的池式铅基快堆，包括反应堆容器、堆顶盖、下封头、堆芯安装构件、堆芯、控制棒及其驱动机构、冷热池隔板、第一辅助隔板、热交换器以及驱动泵；其中，
所述反应堆容器呈中空柱状，其顶端与所述堆顶盖相连后形成密封连接，底端与所述下封头相连后形成密封连接；
所述堆顶盖上设有用于液体或气体进出的第一进出口和第二进出口；
所述堆芯安装构件设置于所述反应堆容器中并位于所述下封头的上方，其顶部设有用于安装所述堆芯的安装位；
所述堆芯安装于所述堆芯安装构件顶部的安装位上；
所述控制棒及其驱动机构的一端位于所述反应堆容器的外部，另一端穿过所述堆顶盖并进入所述反应堆容器中与所述堆芯的顶部相连；
所述冷热池隔板设置于所述反应堆容器中并套设在所述控制棒及其驱动机构的外部，其呈中空锥状，椎体底部与所述堆顶盖相连后形成密封连接，椎体顶部套接在所述堆芯的外壁上后形成密封连接；其中，所述冷热池隔板将所述反应堆容器隔离成互不连通的热池和冷池；所述热池是由所述堆芯、冷热池隔板和堆顶盖三者围成的，其内部容纳有通过所述第一进出口进出的第一冷却剂和第一惰性气体；所述冷池是由所述反应堆容器中除所述热池之外的剩余腔体空间形成，其内部容纳有通过所述第二进出口进出的第二冷却剂和第二惰性气体；
所述第一辅助隔板包括水平隔板以及沿所述水平隔板的四周边缘同时 朝向所述堆顶盖方向延伸形成的竖直隔板；其中，所述水平隔板的中间部位套接在所述冷热池隔板的外壁上并与所述冷热池隔板形成密封连接；所述竖直隔板朝向所述冷热池隔板设置，并与所述冷热池隔板之间预留有一定的距离；
所述热交换器至少有一个，且每一个热交换器的一端均位于所述反应堆容器的外部，另一端均依次穿过所述堆顶盖、所述冷热池隔板形成的热池后进入所述冷池中并位于所述第一辅助隔板和所述冷热池隔板之间预留的间隙内；
所述驱动泵至少有一个，且每一个驱动泵的一端均位于所述反应堆容器的外部，另一端均穿过所述堆顶盖进入所述冷池中并位于所述第一辅助隔板远离所述堆芯的一侧。
其中，还包括：与每一个热交换器对应设置的第二辅助隔板；其中，
每一个第二辅助隔板的一端均与所述冷热池隔板的侧壁相连，另一端均平行于其对应的热交换器的中心轴线方向延伸并位于所述第一辅助隔板和所述冷热池隔板之间预留的间隙内。
其中，还包括：堆顶塞；所述堆顶塞设置于所述热池中，并套接于所述控制棒及其驱动机构的外壁，且靠近所述堆顶盖设置。
其中，所述冷热池隔板的侧壁包括依序垂直相连的第一侧壁、第二侧壁及第三侧壁；其中，
所述第一侧壁与所述堆顶盖垂直连接，其远离所述第二侧壁的一端朝向所述堆顶盖并与所述堆顶盖相连后形成密封连接；
所述第二侧壁与所述第一侧壁相平行，且其与所述第三侧壁相连的一端靠近所述控制棒及其驱动机构设置；其中，每一个热交换器均穿过所述第二侧壁进入所述冷池中并位于所述第一辅助隔板和所述冷热池隔板之间预留的间隙内；
所述第三侧壁与所述第一侧壁相平行，且其远离所述第二侧壁的一端朝向所述堆芯并与所述堆芯相连后形成密封连接。
其中，所述第一辅助隔板的水平隔板与所述冷热池隔板的第二侧壁相平行，所述第一辅助隔板的竖直隔板与所述冷热池隔板的第一侧壁及第三侧壁 相平行。
其中，所述堆芯安装构件呈中空锥状，其椎体底部设有径向贯穿并与所述反应堆容器导通成回路的通道，椎体顶部设有用于安装所述堆芯的安装位。
其中，所述通道的横截面呈波浪形。
其中，还包括：设置于所述反应堆容器和所述堆顶盖之间的耐高温混凝土层。
其中，所述每一个热交换器均为传热管。
其中，所述第一冷却剂和所述第二冷却剂均为液态金属铅或铅铋合金；所述第一惰性气体和所述第二惰性气体均为氩气。
实施本发明实施例，具有如下有益效果：
1、本发明通过冷热池隔板将反应堆容器分隔成互不连通的热池和冷池，热池中的第一冷却剂通过浸没式同时连接热池和冷池的热交换器两端形成的热量差来实现流动，因此不再需设置管道，不仅降低了反应堆堆内构件的复杂性，提高了反应堆运行的可靠性，还降低了一回路冷却剂的流动阻力，从而降低驱动泵的功率要求。
2、本发明通过第一辅助隔板来阻挡热交换器发生传热管破裂时微小汽泡或水滴直接下沉，增加了微小汽泡或水滴破裂时间，从而能避免微小汽泡或水滴直接进入反应堆堆芯的风险，同时第一辅助隔板的水平隔板，在出现地震或晃动的情况下，可减缓冷却剂液面晃动幅度，从而降低堆内构件和主容器的力学冲击，提高了整个反应堆装置的抵抗地震或晃动的性能。
附图说明
为了更清楚地说明本发明实施例或现有技术中的技术方案，下面将对实施例或现有技术描述中所需要使用的附图作简单地介绍，显而易见地，下面描述中的附图仅仅是本发明的一些实施例，对于本领域普通技术人员来讲，在不付出创造性劳动的前提下，还可以根据这些附图获得其他的附图。
图1为本发明实施例提供的具有迷宫式流道的池式铅基快堆的平面剖视图。
具体实施方式
以下各实施例的说明是参考附图，用以示例本发明可以用以实施的特定实施例。
如图1所示，为本发明实施例中，提供的一种具有迷宫式流道的池式铅基快堆，包括反应堆容器1、堆顶盖2、下封头3、堆芯安装构件4、堆芯5、控制棒及其驱动机构6、冷热池隔板7、第一辅助隔板8、热交换器9以及驱动泵10；其中，
反应堆容器1呈中空柱状，其顶端与堆顶盖2相连后形成密封连接，底端与下封头3相连后形成密封连接；在一个例子中，反应堆容器1采用中空圆筒金属容器，堆顶盖2采用钢材制作而成并盖设在反应堆容器1顶端并形成密封连接，下封头3为半球形或椭圆形的封头与反应堆容器1底端形成密封连接，使得整个反应堆容器1、堆顶盖2和下封头3形成一个密封式罐体；
堆顶盖2上设有用于液体或气体进出的第一进出口21和第二进出口22，便于冷却剂和惰性气体注入密封式罐体内；应当说明的是，第一进出口21和第二进出口22的数量可以根据实际进行设计成多个；
堆芯安装构件4设置于反应堆容器1中并位于下封头3的上方，其顶部设有用于安装堆芯5的安装位；在一个例子中，堆芯安装构件4采用钢材制作而成的中空锥体结构，该椎体底部设有径向贯穿并与反应堆容器1导通成回路的通道41，椎体顶部设有用于安装堆芯5的安装位，堆芯安装构件4采用上述中空锥体结构是有利于反应堆容器1中的冷却剂能够进入堆芯安装构件4内并能与堆芯5接触实现换热效果；
堆芯5安装于堆芯安装构件4顶部的安装位上；
控制棒及其驱动机构6的一端位于反应堆容器1的外部，另一端穿过堆顶盖2并进入反应堆容器1中与堆芯5的顶部相连；可以理解的是，控制棒驱动机构位于反应堆容器1的外部，控制帮伸入反应堆容器1中与堆芯5的顶部相连；
冷热池隔板7采用钢材制作而成，设置于反应堆容器1中并套设在控制棒及其驱动机构6的外部，其呈中空锥状，椎体底部朝向堆顶盖2并与堆顶盖2相连后形成密封连接，椎体顶部朝向堆芯5并套接在堆芯5的外壁上后形成密封连接；其中，冷热池隔板7将反应堆容器1隔离成互不连通的热池 T1和冷池T2；热池T1是由堆芯5、冷热池隔板7和堆顶盖2三者围成的，其内部容纳有通过第一进出口21进出的第一冷却剂和第一惰性气体；冷池T2是由反应堆容器1中除热池11之外的剩余腔体空间形成，其内部容纳有通过第二进出口22进出的第二冷却剂和第二惰性气体；在一个例子中，第一冷却剂和第二冷却剂均为液态金属铅或铅铋合金；第一惰性气体和第二惰性气体均为氩气；
第一辅助隔板8采用钢材制作而成，包括水平隔板81以及沿水平隔板81的四周边缘同时朝向堆顶盖2方向延伸形成的竖直隔板82；其中，水平隔板81的中间部位套接在冷热池隔板7的外壁上并与冷热池隔板7形成密封连接，这样能够避免第一辅助隔板8和冷热池隔板7之间包围的第二冷却剂直接下沉与堆芯2进行接触，从而能够防止第一辅助隔板8和冷热池隔板7之间包围的第二冷却剂内产生的微小汽泡或水滴直接进入堆芯2的危险；竖直隔板82朝向冷热池隔板7设置，并与冷热池隔板7之间预留有一定的距离，可以延长第一辅助隔板8和冷热池隔板7之间包围的第二冷却剂内产生的微小汽泡或水滴破灭的时间；
热交换器9至少有一个，且每一个热交换器9的一端均位于反应堆容器1的外部，另一端均依次穿过堆顶盖2、冷热池隔板7形成的热池T1后进入冷池T2中并位于第一辅助隔板8和冷热池隔板7之间预留的间隙内，使得热池T1能利用热交换器9两端的热量差实现池内第一冷却剂的流动，将堆芯5热量带走并传导至冷池T2中实现堆芯5换热效果，同时一旦热交换器9在冷池T2中出现破裂时第二冷却剂内所产生的小汽泡或水滴，能被第一辅助隔板8和冷热池隔板7有效阻挡住；在一个例子中，热交换器9有多个，沿控制棒的四周环状布置，且均为传热管；
驱动泵10至少有一个，且每一个驱动泵10的一端均位于反应堆容器1的外部，另一端均穿过堆顶盖2进入冷池T2中并位于第一辅助隔板8远离堆芯5的一侧；可以理解的是，驱动泵10启动后，加速冷池T2中第二冷却剂的循环流速，加快对堆芯5的换热效果；在一个例子中，驱动泵10有多个，每一个驱动泵10顶端的电机驱动机构位于反应堆容器1的外部，底端的搅拌棒位于冷池T2中。
应当说明的是，所有部件的顶端、底端、顶部及底部都是以堆顶盖2为参照物，朝向堆顶盖2方向的一端为顶端或顶部，远离堆顶盖2方向的一端为底端或底部。
在本发明实施例中，还包括：与每一个热交换器9对应设置的第二辅助隔板11；其中，每一个第二辅助隔板11均采用钢材制作而成，其一端均与冷热池隔板7的侧壁相连，另一端均平行于其对应的热交换器9的中心轴线方向延伸并位于第一辅助隔板8和冷热池隔板7之间预留的间隙内，从而使得第二辅助隔板11和第一辅助隔板8进行交错设置成迷宫式的流道，在热交换器9出现破裂时冷池T2中第二冷却剂内所产生的小汽泡或水滴破灭时间进一步得到延长。
在本发明实施例中，还包括：采用钢材制作而成的堆顶塞12；堆顶塞12设置于热池T1中，并套接于控制棒及其驱动机构6的外壁，且靠近堆顶盖2设置，该堆顶塞12提供支持和贯穿通道，在换料期间可以拆卸，提供换料通道。
在本发明实施例中，冷热池隔板7为阶梯状的椎体结构，其侧壁包括依序垂直相连的第一侧壁71、第二侧壁72及第三侧壁73；其中，
第一侧壁71与堆顶盖2垂直连接，其远离第二侧壁72的一端朝向堆顶盖2并与堆顶盖2相连后形成密封连接；
第二侧壁72与第一侧壁71相平行，且其与第三侧壁73相连的一端靠近控制棒及其驱动机构6设置；其中，每一个热交换器9均穿过第二侧壁72进入冷池T2中并位于第一辅助隔板8和冷热池隔板7之间预留的间隙内；
第三侧壁73与第一侧壁71相平行，且其远离第二侧壁72的一端朝向堆芯5并与堆芯5相连后形成密封连接。
可以理解的是，冷热池隔板7采用阶梯状的椎体结构，有利于热交换器9的安装以及加大热交换器9在热池T1中的换热面积。
在本发明实施例中，第一辅助隔板8的水平隔板81与冷热池隔板7的第二侧壁72相平行，第一辅助隔板8的竖直隔板82与冷热池隔板7的第一侧壁71及第三侧壁73相平行。
在本发明实施例中，堆芯安装构件4的通道41的横截面呈波浪形，这 样有利于加快第二冷却剂的流速。
在本发明实施例中，还包括：设置于反应堆容器1和堆顶盖2之间的耐高温混凝土层13，这样有利于避免反应堆容器1中液态冷却剂的蒸发。
实施本发明实施例，具有如下有益效果：
1、本发明通过冷热池隔板将反应堆容器分隔成互不连通的热池和冷池，热池中的第一冷却剂通过浸没式同时连接热池和冷池的热交换器两端形成的热量差来实现流动，因此不再需设置管道，不仅降低了反应堆堆内构件的复杂性，提高了反应堆运行的可靠性，还降低了一回路冷却剂的流动阻力，从而降低驱动泵的功率要求。
2、本发明通过第一辅助隔板来阻挡热交换器发生传热管破裂时微小汽泡或水滴直接下沉，增加了微小汽泡或水滴破裂时间，从而能避免微小汽泡或水滴直接进入反应堆堆芯的风险，同时第一辅助隔板的水平隔板，在出现地震或晃动的情况下，可减缓冷却剂液面晃动幅度，从而降低堆内构件和主容器的力学冲击，提高了整个反应堆装置的抵抗地震或晃动的性能。
以上所揭露的仅为本发明较佳实施例而已，当然不能以此来限定本发明之权利范围，因此依本发明权利要求所作的等同变化，仍属本发明所涵盖的范围。

Claims (10)

  1. 一种具有迷宫式流道的池式铅基快堆，其特征在于，包括反应堆容器(1)、堆顶盖(2)、下封头(3)、堆芯安装构件(4)、堆芯(5)、控制棒及其驱动机构(6)、冷热池隔板(7)、第一辅助隔板(8)、热交换器(9)以及驱动泵(10)；其中，
    所述反应堆容器(1)呈中空柱状，其顶端与所述堆顶盖(2)相连后形成密封连接，底端与所述下封头(3)相连后形成密封连接；
    所述堆顶盖(2)上设有用于液体或气体进出的第一进出口(21)和第二进出口(22)；
    所述堆芯安装构件(4)设置于所述反应堆容器(1)中并位于所述下封头(3)的上方，其顶部设有用于安装所述堆芯(5)的安装位；
    所述堆芯(5)安装于所述堆芯安装构件(4)顶部的安装位上；
    所述控制棒及其驱动机构(6)的一端位于所述反应堆容器(1)的外部，另一端穿过所述堆顶盖(2)并进入所述反应堆容器(1)中与所述堆芯(5)的顶部相连；
    所述冷热池隔板(7)设置于所述反应堆容器(1)中并套设在所述控制棒及其驱动机构(6)的外部，其呈中空锥状，椎体底部与所述堆顶盖(2)相连后形成密封连接，椎体顶部套接在所述堆芯(5)的外壁上后形成密封连接；其中，所述冷热池隔板(7)将所述反应堆容器(1)隔离成互不连通的热池(T1)和冷池(T2)；所述热池(T1)是由所述堆芯(5)、冷热池隔板(7)和堆顶盖(2)三者围成的，其内部容纳有通过所述第一进出口(21)进出的第一冷却剂和第一惰性气体；所述冷池(T2)是由所述反应堆容器(1)中除所述热池(11)之外的剩余腔体空间形成，其内部容纳有通过所述第二进出口(22)进出的第二冷却剂和第二惰性气体；
    所述第一辅助隔板(8)包括水平隔板(81)以及沿所述水平隔板(81)的四周边缘同时朝向所述堆顶盖(2)方向延伸形成的竖直隔板(82)；其中，所述水平隔板(81)的中间部位套接在所述冷热池隔板(7)的外壁上并与所述冷热池隔板(7)形成密封连接；所述竖直隔板(82)朝向所述冷热池隔板(7)设置，并与所述冷热池隔板(7)之间预留有一定的距离；
    所述热交换器(9)至少有一个，且每一个热交换器(9)的一端均位于所述反应堆容器(1)的外部，另一端均依次穿过所述堆顶盖(2)、所述冷热池隔板(7)形成的热池(T1)后进入所述冷池(T2)中并位于所述第一辅助隔板(8)和所述冷热池隔板(7)之间预留的间隙内；
    所述驱动泵(10)至少有一个，且每一个驱动泵(10)的一端均位于所述反应堆容器(1)的外部，另一端均穿过所述堆顶盖(2)进入所述冷池(T2)中并位于所述第一辅助隔板(8)远离所述堆芯(5)的一侧。
  2. 如权利要求1所述的具有迷宫式流道的池式铅基快堆，其特征在于，还包括：与每一个热交换器(9)对应设置的第二辅助隔板(11)；其中，每一个第二辅助隔板(11)的一端均与所述冷热池隔板(7)的侧壁相连，另一端均平行于其对应的热交换器(9)的中心轴线方向延伸并位于所述第一辅助隔板(8)和所述冷热池隔板(7)之间预留的间隙内。
  3. 如权利要求2所述的具有迷宫式流道的池式铅基快堆，其特征在于，还包括：堆顶塞(12)；所述堆顶塞(12)设置于所述热池(T1)中，并套接于所述控制棒及其驱动机构(6)的外壁，且靠近所述堆顶盖(2)设置。
  4. 如权利要求3所述的具有迷宫式流道的池式铅基快堆，其特征在于，所述冷热池隔板(7)的侧壁包括依序垂直相连的第一侧壁(71)、第二侧壁(72)及第三侧壁(73)；其中，
    所述第一侧壁(71)与所述堆顶盖(2)垂直连接，其远离所述第二侧壁(72)的一端朝向所述堆顶盖(2)并与所述堆顶盖(2)相连后形成密封连接；
    所述第二侧壁(72)与所述第一侧壁(71)相平行，且其与所述第三侧壁(73)相连的一端靠近所述控制棒及其驱动机构(6)设置；其中，每一个热交换器(9)均穿过所述第二侧壁(72)进入所述冷池(T2)中并位于所述第一辅助隔板(8)和所述冷热池隔板(7)之间预留的间隙内；
    所述第三侧壁(73)与所述第一侧壁(71)相平行，且其远离所述第二侧壁(72)的一端朝向所述堆芯(5)并与所述堆芯(5)相连后形成密封连接。
  5. 如权利要求4所述的具有迷宫式流道的池式铅基快堆，其特征在于， 所述第一辅助隔板(8)的水平隔板(81)与所述冷热池隔板(7)的第二侧壁(72)相平行，所述第一辅助隔板(8)的竖直隔板(82)与所述冷热池隔板(7)的第一侧壁(71)及第三侧壁(73)相平行。
  6. 如权利要求5所述的具有迷宫式流道的池式铅基快堆，其特征在于，所述堆芯安装构件(4)呈中空锥状，其椎体底部设有径向贯穿并与所述反应堆容器(1)导通成回路的通道(41)，椎体顶部设有用于安装所述堆芯(5)的安装位。
  7. 如权利要求6所述的具有迷宫式流道的池式铅基快堆，其特征在于，所述通道(41)的横截面呈波浪形。
  8. 如权利要求7所述的具有迷宫式流道的池式铅基快堆，其特征在于，还包括：设置于所述反应堆容器(1)和所述堆顶盖(2)之间的耐高温混凝土层(13)。
  9. 如权利要求8所述的具有迷宫式流道的池式铅基快堆，其特征在于，所述每一个热交换器(9)均为传热管。
  10. 如权利要求9所述的具有迷宫式流道的池式铅基快堆，其特征在于，所述第一冷却剂和所述第二冷却剂均为液态金属铅或铅铋合金；所述第一惰性气体和所述第二惰性气体均为氩气或其他惰性气体。
PCT/CN2020/072687 2019-01-25 2020-01-17 一种具有迷宫式流道的池式铅基快堆 WO2020151588A1 (zh)

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