WO2023077672A1 - 核反应装置及净化系统 - Google Patents

核反应装置及净化系统 Download PDF

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Publication number
WO2023077672A1
WO2023077672A1 PCT/CN2022/071393 CN2022071393W WO2023077672A1 WO 2023077672 A1 WO2023077672 A1 WO 2023077672A1 CN 2022071393 W CN2022071393 W CN 2022071393W WO 2023077672 A1 WO2023077672 A1 WO 2023077672A1
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WIPO (PCT)
Prior art keywords
module
heat exchange
reaction
purification
nuclear
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Application number
PCT/CN2022/071393
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English (en)
French (fr)
Inventor
梁活
杨江
沈永刚
陈忆晨
刘建昌
路长冬
刘仲昊
陈韵茵
崔旭阳
纪文英
鲍小丽
王仙茅
欧阳勇
卢向晖
刘金林
Original Assignee
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
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Publication of WO2023077672A1 publication Critical patent/WO2023077672A1/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
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • 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
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
    • 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

  • This application relates to the technical field of nuclear reaction, especially nuclear reaction device and purification system.
  • the problem of heat transfer and the hazard of radioactive elements In the application of nuclear reaction, at least two aspects need to be considered: the problem of heat transfer and the hazard of radioactive elements.
  • Most of the existing nuclear reactors adopt the external heat exchange method, that is, the reactor and the heat exchange module are installed separately, which leads to a large overall design volume of the reactor, which does not conform to the miniaturization design idea of the reactor.
  • the external heat exchange method also has problems
  • due to the presence of radioactive elements in the cooling liquid of nuclear reactors it is necessary to maintain a low level of radioactive elements in the cooling liquid to reduce the damage to the staff and improve the safety of the reactor.
  • a nuclear reactor comprising:
  • a reaction vessel is provided with a reaction chamber and a top cover for closing the reaction chamber;
  • reaction module arranged in the reaction chamber, the reaction module reacts and releases heat in the reaction chamber
  • a heat exchange module is arranged in the reaction chamber, the heat exchange module can absorb the heat released by the reaction module, the inlet of the heat exchange module is used to communicate with the liquid supply system, and the outlet of the heat exchange module is used for Communication with thermal drive system.
  • the heat exchange module is housed in the reaction chamber of the reaction vessel to utilize the inner space of the reaction vessel, so that the overall volume of the nuclear reaction device is smaller, which is more in line with the miniaturization design of the nuclear reaction device.
  • the reaction module can be a nuclear reaction module, which releases heat during the reaction process. Since the heat exchange module and the reaction module are located in the reaction chamber, the heat released by the reaction module can be directly absorbed by the heat exchange module, and the absorption rate is high. In terms of external heat exchange modules, the nuclear reactor can also improve the heat exchange utilization rate of the reaction modules.
  • the heat exchange module includes at least one set of heat exchange tube bundles, the inlet of each set of heat exchange tube bundles is used to communicate with the liquid supply system, and the outlet of each set of heat exchange tube bundles is used for In communication with the thermal drive system.
  • the heat exchange tube bundle is helically wound on the outer wall of the reaction module.
  • multiple sets of the heat exchange tube bundles are arranged circumferentially along the outer wall of the reaction module.
  • the nuclear reaction device further includes a positioning plate, the positioning plate is fixedly arranged on the outer wall of the reaction module, and the positioning plate is provided with the same number of positioning holes as the heat exchange tube bundles, so as to respectively fix Multiple sets of heat exchange tube bundles.
  • the nuclear reaction device further includes a fixing assembly, the fixing assembly is arranged on the top cover, the reaction module is located in the fixing assembly, the fixing assembly fixes the positioning plate, the The heat exchange tube bundle is arranged on the outer wall of the fixing assembly.
  • the fixing assembly includes a hanging basket and a flange, the flange fixes the hanging basket on the top cover, the reaction module is located in the hanging basket, and the hanging basket
  • the outer wall of the basket is provided with a connecting piece to fix the positioning plate, and the heat exchange tube bundle is provided on the outer wall of the hanging basket.
  • the reaction chamber is filled with cooling liquid
  • the side of the hanging basket away from the top cover is provided with a lower head
  • the lower head is provided with a first distribution hole, and the first The distribution hole communicates with the reaction chamber and the hanging basket;
  • the nuclear reaction device also includes a cooling liquid circulation module, the cooling liquid module drives the cooling liquid in the reaction vessel to the positioning plate, and the positioning plate is provided with a plurality of first holes for the cooling liquid to flow through. Two orifices.
  • the reaction module includes a core arranged in the hanging basket, a control rod assembly reacting with the core, and a driving mechanism for driving the control rod assembly to move.
  • a purification system including the nuclear reactor, the purification system also includes a first purification module and a second purification module;
  • the first purification module is in communication with the nuclear reactor, and is used to accommodate and circulate the coolant of the nuclear reactor;
  • the second purification module is in circulation communication with the first purification module, and the second purification module aerates the first purification module and purifies the fluid in the first purification module.
  • the first purification module includes a connected mixing box and a static box
  • the mixing tank and the static tank are respectively communicated with the nuclear reactor, and the cooling liquid of the nuclear reactor can flow into the mixing tank and flow into the nuclear reactor from the static tank;
  • the aeration inlet and aeration outlet of the mixing box are respectively communicated with the second purification module.
  • the air injection device there is an air injection device inside the mixing box, and the air injection device communicates with the aeration inlet of the mixing box.
  • the air injection device includes multiple sets of circular pipes arranged concentrically, a connecting pipe connecting the multiple sets of circular pipes, and an air intake main pipe communicating with the connecting pipes, the air intake main pipe
  • the tubes communicate with the aeration inlet of the mixing box, and each circular tube is provided with a plurality of nozzles.
  • the static box is shaped as a box with hemispherical ends and a cylindrical middle.
  • At least one circular orifice plate and multiple half-moon orifice plates are arranged in the static box.
  • the second purification module includes at least one set of filtering devices.
  • the first purification module further includes a drain line, and the drain line communicates with the nuclear reactor and the mixing tank; a transfer line and a A balance pipeline; the static tank communicates with the nuclear reaction device through an upstroke pipeline, and the upstroke pipeline is provided with an upstroke pump.
  • a pressure sensor is provided in the mixing tank, and the pressure sensor can calculate the liquid level of the mixing tank according to the pressure in the mixing tank, and the pressure sensor is electrically connected with the main control room .
  • the second purification module further includes a purification line connecting the aeration outlet of the mixing tank with the inlet of the filter device, and the outlet of the filter device is communicated with the inlet of the first circulation line ;
  • the first circulation pipeline is provided with a gas compression pump, and the outlet of the first circulation pipeline communicates with the aeration inlet of the mixing tank through the second circulation pipeline, and communicates with the gas recovery tank through the gas return pipeline, and the gas
  • the recovery box supplies gas to the first circulation pipeline through the gas supply pipeline.
  • the second purification module further includes an air cavity downflow pipe connecting the nuclear reaction device and the inlet of the filter device; a valve is also arranged between the outlet of the first circulation line and the nuclear reaction device Flushing pipe on the air cavity.
  • Fig. 1 is the schematic structural view of the nuclear reactor in an embodiment of the present application
  • Fig. 2 is a schematic structural diagram of a heat exchange module in an embodiment of the present application
  • Fig. 3 is a schematic structural diagram of a heat exchange module in another embodiment of the present application.
  • FIG. 4 is a schematic structural view of a positioning plate in an embodiment of the present application.
  • Figure 5 is a schematic structural view of a nuclear reactor in another embodiment of the present application.
  • Fig. 6 is a schematic diagram of the structure of the hanging basket in an embodiment of the present application.
  • Fig. 7 is a schematic structural diagram of a flow guide assembly in an embodiment of the present application.
  • Fig. 8 is a top view of the guide assembly in Fig. 7;
  • Fig. 9 is a schematic diagram of a purification system in an embodiment of the present application.
  • FIG. 10 is a schematic structural view of a circular orifice plate in an embodiment of the present application.
  • Fig. 11 is a schematic structural diagram of an air injection device in an embodiment of the present application.
  • Fig. 12 is another schematic diagram of the air injection device in Fig. 11;
  • Fig. 13 is a schematic diagram of a purification system in another embodiment of the present application.
  • heat exchange module 300, heat exchange module; 310, heat exchange tube bundle; 320, deflector assembly; 321, baffle plate;
  • Second purification module 810. Filtration device; 811. Isolation valve; 820. Purification pipeline;
  • first and second are used for descriptive purposes only, and cannot be interpreted as indicating or implying relative importance or implicitly specifying the quantity of indicated technical features.
  • the features defined as “first” and “second” may explicitly or implicitly include at least one of these features.
  • “plurality” means at least two, such as two, three, etc., unless otherwise specifically defined.
  • a first feature being "on” or “under” a second feature may mean that the first and second features are in direct contact, or that the first and second features are indirect through an intermediary. touch.
  • “above”, “above” and “above” the first feature on the second feature may mean that the first feature is directly above or obliquely above the second feature, or simply means that the first feature is higher in level than the second feature.
  • “Below”, “beneath” and “beneath” the first feature may mean that the first feature is directly below or obliquely below the second feature, or simply means that the first feature is less horizontally than the second feature.
  • Nuclear reactors can convert chemical energy or nuclear energy into heat to drive related heat-driven systems. For example, nuclear reactors can vaporize water with the heat released to drive turbines. At least two convenient problems need to be paid attention to when the nuclear reactor is used as a nuclear reactor. Most of the existing nuclear reactors adopt the external heat exchange method, that is, the reactor and the heat exchange module are set separately, which leads to a large overall design volume of the reactor, which does not meet the requirements of the reactor. In addition, the way of external heat exchange also has the problem of reducing the utilization rate of heat exchange; on the other hand, due to the presence of radioactive elements in the cooling liquid of nuclear reactors, it is necessary to maintain the radioactive elements in the cooling liquid at a low level. Reduce injuries to workers.
  • the research and development personnel proposed a nuclear reaction device, in which both the reaction module and the heat exchange module are housed in the nuclear reaction device, so as to reduce the overall volume of the nuclear reaction device.
  • the present application also proposes a purification system to purify possible polluting elements or harmful elements that may exist in the nuclear reactor during the reaction process, so as to reduce pollution and ensure the safety of staff and the safety of reactor operation.
  • the nuclear reaction device proposed in this application can be used in nuclear reactor processes, but is not limited thereto.
  • chemical exothermic processes can also be completed by the nuclear reaction device in this application.
  • Fig. 1 shows a schematic structural view of a nuclear reactor in an embodiment of the present application.
  • the nuclear reactor provided in an embodiment of the present application includes: a reaction vessel 100, a reaction module 200 and a heat exchange module 300, and the reaction vessel 100 is used to accommodate the reaction module 200 and the heat exchange module 300, so that the space ratio of the entire nuclear reaction device is smaller, and it is more in line with the design requirements of miniaturization of the nuclear reaction device.
  • the heat released by the reaction module 200 can be directly utilized by the heat exchange module 300 , so compared with the external heat exchange module 300 , the nuclear reaction device in this embodiment can also improve the utilization rate of heat exchange.
  • the reaction module 200 may be a nuclear reactor, for example, may include a core, a control rod assembly, and a driving mechanism for driving the control rod assembly; the reaction module 200 may also be a module including chemical element reaction heat release.
  • the heat exchange module 300 mainly absorbs the heat released by the reaction module 200 during the reaction to facilitate other driving work.
  • the inlet of the heat exchange module 300 is used to communicate with the liquid supply system, and the heat exchange module 300 can transfer the liquid supply
  • the water delivered by the system is vaporized to drive heat-driven systems such as turbines.
  • the reaction vessel 100 is provided with a reaction chamber 110 and a top cover 120 for closing the reaction chamber 110, so that the reaction vessel 100 is a relatively closed space, and the top cover 120 can prevent the temperature loss of the reaction vessel 100 on the one hand; Diffusion of contaminating elements or radioactive elements in the reaction container 100 can be prevented.
  • the reaction module 200 is arranged in the reaction chamber 110, and the reaction module 200 reacts and releases heat in the reaction chamber 110; the heat exchange module 300 is arranged in the reaction chamber 110, and the heat exchange module 300 can absorb the heat released by the reaction module 200, and the heat exchange module 300
  • the inlet of the heat exchange module 300 is used to communicate with the liquid supply system, and the outlet of the heat exchange module 300 is used to communicate with the heat driving system.
  • the heat exchange module 300 may include at least one set of heat exchange tube banks 310 , the inlet of each heat exchange tube bank 310 communicates with the liquid supply system, and the outlet of each heat exchange tube bank 310 communicates with the heat driving system.
  • the reaction module 200 releases heat during operation, and the heat exchange module 300 absorbs the heat of the reaction module 200 and can vaporize the water delivered to the heat exchange module 300 in the liquid supply system, and promote the heat drive system to work. Since the heat exchange module 300 is accommodated in the reaction chamber 110 , the overall volume of the nuclear reactor is smaller, which is more in line with the miniaturization design of the nuclear reactor.
  • the reaction module 200 can be a nuclear reaction module 200.
  • the nuclear reaction module 200 releases heat during the reaction process. Since the heat exchange module 300 and the reaction module 200 are located in the reaction vessel 100, the heat released by the reaction module 200 can be directly absorbed by the heat exchange module 300. , the heat absorption rate is high, so compared with the external heat exchange module 300, the nuclear reactor can also improve the heat exchange utilization rate of the reaction module 200.
  • the inventor thought that it is necessary to place the heat exchange module 300 as close as possible to the reaction module 200, that is, by shortening the distance between the heat exchange module 300 and the reaction module 200, it can be improved as much as possible.
  • the utilization rate of the heat exchange module 300 the inventors wound the heat exchange tube bundle 310 included in the heat exchange module 300 helically on the outer wall of the reaction module 200 , as shown in FIG. 2 .
  • the heat exchange tube bundle 310 in the heat exchange module 300 Since the heat exchange tube bundle 310 in the heat exchange module 300 is spirally wound on the outer wall of the reaction module 200, the heat exchange tube bundle 310 in the heat exchange module 300 has a larger contact area with the outer wall of the reaction module 200, thereby enabling the heat exchange tube bundle 310 better absorbs the heat of the reaction module 200 .
  • the water flow supplied by the liquid supply system can enter from the lower part of the heat exchange tube bank 310, and then flow out from the upper part of the heat exchange tube bank 310.
  • the lower part of the heat exchange tube bank 310 refers to a part near the bottom wall of the reaction vessel 100
  • the upper part of the heat exchange tube bundle 310 refers to the side close to the top cover 120 .
  • the advantage of this design is that it can shorten the flow distance of the water flow in the heat exchange tube bundle 310 , and it is also convenient to discharge the evaporated water vapor directly.
  • multiple sets of heat exchange tube bundles 310 are arranged circumferentially along the outer wall of the reaction module 200 .
  • This solution is different from the previous solution in that the heat exchange tube bundle 310 is arranged close to the outer wall of the reaction module 200 .
  • the spiral radius of the heat exchange tube bundle 310 is smaller than the distance between the reaction vessel 100 and the reaction module 200 .
  • the scheme in this embodiment and the design scheme in the previous embodiment can be selected and designed according to the volume of the reaction chamber 110 of the reaction vessel 100 .
  • the nuclear reaction device further includes a positioning plate 400, wherein the positioning plate 400 is fixedly arranged on the outer wall of the reaction module 200, and the positioning plate 400 is provided with the same number of positioning holes 410 as the heat exchange tube bundle 310, so as to A plurality of heat exchange tube bundles 310 are respectively fixed. In this way, after the position of the positioning plate 400 and the position of the reaction module 200 are fixed, the heat exchange tube bundle 310 can be fixed through its own positioning hole 410 .
  • the reaction module 200 and the heat exchange module 300 are respectively arranged in the reaction container 100, in order to avoid the relative movement between the reaction module 200 and the heat exchange module 300 during the reaction process, thereby affecting the reaction module 200 and the heat exchange module 300 work process.
  • the reaction module 200 is fixed by the fixing assembly 500 .
  • the nuclear reactor further includes a fixing assembly 500, wherein the fixing assembly 500 is arranged on the top cover 120, the reaction module 200 is located in the fixing assembly 500, the fixing assembly 500 fixes the positioning plate 400, and the heat exchange tube bundle 310 is arranged on The outer wall of the assembly 500 is fixed.
  • Fixing the reaction module 200 by the fixing assembly 500 can ensure the stability of the reaction module 200 in the reaction vessel 100 , and further enable the reaction module 200 and the heat exchange module 300 to work normally. Since the fixing assembly 500 is used to accommodate the reaction module 200 , the heat exchange tube bundle 310 in the heat exchange module 300 can be wound around the outer wall of the fixing assembly 500 or circumferentially arranged on the outer wall of the fixing assembly 500 .
  • the fixing assembly 500 includes a hanging basket 510 and a flange 520, wherein the flange 520 fixes the hanging basket 510 on the top cover 120, the reaction module 200 is located in the hanging basket 510, and the hanging basket 510
  • the outer wall of the basket 510 is provided with a connecting piece 511 to fix the positioning plate 400 , the connecting piece 511 can be a buckle, and the heat exchange tube bundle 310 is set on the outer wall of the hanging basket 510 , as shown in FIG. 3 .
  • the hanging basket 510 can be better fixed on the top cover 120 through the flange plate 520 , and the bottom of the hanging basket 510 can be supported by the bottom wall of the reaction vessel 100 .
  • the end of the flange 520 connected to the hanging basket 510 is arranged inside the hanging basket 510 .
  • the cooling liquid can be lead-bismuth alloy, etc., in order to make the cooling liquid circulate in the reaction vessel 100 and flow into the nuclear reactor more evenly to take away the heat released by the nuclear reactor, the inventor thought of setting the cooling liquid
  • the circulation module 600 and the lower head 530 are arranged in the reaction vessel 100 . Specifically, as shown in FIG.
  • the reaction chamber 110 of the reaction vessel 100 is filled with cooling liquid, and the side of the hanging basket 510 away from the top cover 120 is provided with a lower head 530 , for example, the lower head 530 can be clamped. It is fixed with the hanging basket 510 or supported by the hanging basket 510 , wherein the lower head 530 is provided with a first distribution hole 531 , and the first distribution hole 531 communicates with the reaction chamber 110 of the reaction vessel 100 and the hanging basket 510 .
  • the cooling liquid can enter the hanging basket 510 from the first distribution hole 531; the nuclear reaction device also includes a cooling liquid circulation module 600, and the cooling liquid module drives the cooling liquid of the reaction vessel 100 to the positioning plate 400, and multiple positioning plates 400 are provided for The cooling liquid flows through the second distribution hole 420 .
  • the number of cooling fluid circulation modules 600 may be multiple.
  • the cooling liquid circulation module 600 can drive the cooling liquid in the reaction vessel 100 to the positioning plate 400. Since the cooling liquid absorbs the heat of the reaction module 200, the cooling liquid can transfer heat when it is driven to the positioning plate 400.
  • the heat exchange tube bundle 310 below the positioning plate 400 is given.
  • the second flow distribution hole 420 is provided on the positioning plate 400 , which can make the flow rate of the cooling liquid on the positioning plate 400 more uniform, so that the cooling liquid can better exchange heat with the heat exchange tube bundle 310 .
  • the cooling liquid After the cooling liquid flows from the positioning plate 400 from the heat exchange tube bundle 310 into the lower head 530, the cooling liquid can enter the hanging basket 510 from the first distribution hole 531 of the lower head 530 to absorb the heat of the reaction module 200 again. heat.
  • the cooling liquid circulation system is described as an example.
  • the cooling liquid circulation system includes a pump and a delivery pipeline, the pump is arranged on the delivery pipeline, and the delivery pipeline communicates with the reaction chamber 110 of the reaction vessel 100 .
  • the pump works, it can draw the cooling liquid into the delivery pipeline, and drive it to flow to the positioning plate 400 .
  • the delivery pipeline can adopt a double-layer pipeline, that is, by setting an opening on the reaction vessel 100, it is possible to complete the cooling liquid entering the delivery pipeline and from the delivery pipeline. discharge.
  • the heat exchange tube bundles 310 When the heat exchange tube bundles 310 are arranged in the circumferential direction of the outer wall of the hanging basket 510, there may be a gap between two adjacent heat exchange tube bundles 310, and when the cooling liquid flows to the heat exchange tube bundles 310, it may flow through the gap between the heat exchange tube bundles 310, This is not conducive to the heat transfer of the cooling liquid to the heat exchange tube bundle 310 .
  • the inventor conceived of setting the flow guide assembly 320 to accommodate the heat exchange tube bundles 310 , thereby preventing the cooling liquid from flowing through the gaps between the heat exchange tube bundles 310 . Specifically, as shown in FIG. 7 and FIG.
  • the deflector assembly 320 includes oppositely arranged spoilers 321 and a deflector cylinder 322 located between the spoilers 321 , the deflector cylinder 322 and the spoiler 321 are sleeved on the On the outer wall of the hanging basket 510, the air guide cylinder 322 is provided with a plurality of accommodation cavities 3221 to accommodate the heat exchange tube bundles, and the spoiler 321 is provided with accommodation holes 3211 communicating with the accommodation chambers 3221 so that the heat exchange tube bundles 310 can enter the air guide cylinder 322 accommodating cavity 3221.
  • the guide tube 322 and the spoiler 321 can be sleeved on the outer wall of the hanging basket 510 by setting through holes, and the heat exchange tube bundle 310 is placed in the accommodation cavity 3221 of the guide tube 322, and the cooling liquid flows to The heat exchange tube bundle 310 flows through the receiving cavity 3221 of the air guide tube 322 , so that the cooling liquid can transfer heat to the heat exchange tube bundle 310 more fully, thereby further improving the heat absorption efficiency of the heat exchange tube bundle.
  • an isolation box 130 is provided on the side of the top cover 120 away from the reaction vessel 100, as shown in FIG. .
  • the water supply loop box is connected to the liquid supply system and the inlet of the heat exchange module 300
  • the steam loop box is connected to the thermal drive system and the outlet of the heat exchange module 300 .
  • the isolation box 130 can better play the role of buffering water flow and air flow.
  • the reactor module 200 when the nuclear reactor is used in a nuclear reaction process, the reactor module 200 includes a reactor core 210 arranged in a hanging basket 510, a control rod assembly 220 reacting with the reactor core 210, and a driving control rod assembly 220 is moved by drive mechanism 230 .
  • the reaction process of the reaction module 200 is that the driving mechanism 230 drives the control rod assembly 220 to move so that the control rod assembly 220 reacts with the core 210 and releases heat.
  • the working principle of this embodiment is that the driving mechanism 230 drives the control rod assembly 220 to move, and then controls the power of the core 210 for nuclear reaction and heat release.
  • the liquid supply system delivers water to the heat exchange tube bundle 310 of the heat exchange module 300 through the isolation box 130.
  • the reaction vessel 100 is filled with coolant, which can absorb the heat released by the nuclear reaction in the core 210.
  • the coolant circulation module 600 drives the coolant to to the positioning plate 400, further through the second distribution hole 420 on the positioning plate 400 and the heat exchange module 300, the water flow in the heat exchange tube bank 310 of the heat exchange module 300 absorbs heat and vaporizes, and the water flow in the heat exchange tube bank 310 is vaporized to push the heat Drive System.
  • the coolant can flow into the core 210 from the first distribution hole 531 of the lower head 530 to absorb the heat of the core 210 again.
  • the heat exchange module 300 since the heat exchange module 300 is built in, the volume of the entire nuclear reaction device is reduced, which conforms to the design idea of miniaturization of the nuclear reaction device.
  • the heat exchange tube bundle 310 in the heat exchange module 300 is wound helically on the outer wall of the hanging basket 510 or arranged circumferentially on the outer wall of the hanging basket 510 , it can better absorb heat during the nuclear reaction.
  • the second flow distribution hole 420 on the positioning plate 400 makes the flow rate of the coolant under the positioning plate 400 more uniform, which can also improve the heat absorption efficiency of the heat exchange tube bundle 310 .
  • the first distribution hole 531 provided on the lower head 530 can make the cooling liquid enter or flow out more uniformly.
  • nuclear reactors may release polluting elements or radioactive elements during the reaction process, these elements need to be purified.
  • the cooling liquid contains radioactive elements
  • the radioactive elements in the cooling liquid are not kept at a low level, the safety of the operator may be endangered, and the nuclear reaction process may also be affected.
  • the inventor thought of setting up an online purification system to be able to automatically absorb the radioactive elements in the cooling liquid in the nuclear reaction.
  • the idea of this application is to design two purification modules, namely the first purification module 700 and the second purification module 800, the first purification module 700 is used to accommodate the coolant, and the second purification module 800 is used to supply the cooling liquid to the first purification module 700.
  • the second purification module 800 purifies.
  • the gas that the second purification module 800 aerates into the first purification module 700 may be helium, carbon dioxide or nitrogen, or a mixture of these gases.
  • the purification system further includes a first purification module 700 and a second purification module 800 .
  • the first purification module 700 communicates with the nuclear reactor, and is used to contain and circulate the coolant of the nuclear reactor;
  • the second purification module 800 is in circulation communication with the first purification module 700, and the second purification module 800 aerates the first purification module 700 And purify the fluid in the first purification module 700 .
  • the coolant of the nuclear reactor can enter the first purification module 700, and the second purification module 800 aerates into the first purification module 700, so that the coolant contained in the first purification module 700 is stirred, thereby cooling release more radioactive elements into the liquid.
  • the radioactive elements released in the cooling liquid can enter into the second purification module 800 and be purified by the second purification module 800 .
  • at least two communication pipes 732 may be provided between the first purification module 700 and the second purification module 800, and one of the communication pipes 732 is used for the second purification module 800 to aerate the first purification module 700, Another communication pipe 732 is used for the airflow in the first purification module 700 to enter the second purification module 800 .
  • the second purification module 800 may include at least one set of filter devices 810 .
  • the radioactive elements of the nuclear reactor can be kept at a low level, which can reduce the radiation impact of the nuclear reactor on the workers, and can also make the nuclear reactor more efficient. run well.
  • the first purification module 700 includes a mixing box 710 and a static box 720 which are connected. Wherein the mixing box 710 and the static box 720 are communicated with the nuclear reactor respectively, and the cooling liquid of the nuclear reactor can flow into the mixing box 710 and flow into the nuclear reactor from the static box 720; the aeration inlet and the aeration outlet of the mixing box 710 are connected with the nuclear reactor respectively.
  • the second purification module 800 is connected, and the second purification module 800 aerates the mixing box 710 and purifies the airflow discharged from the mixing box 710 .
  • the cooling liquid first enters the mixing tank 710, and then the second purification module 800 aerates the mixing tank 710 through the aeration inlet of the mixing tank 710, so that the cooling liquid in the mixing tank 710 can be fully stirred
  • the radioactive elements contained in the cooling liquid can enter the second purification module 800 from the aeration outlet of the mixing box 710 along with the airflow, and thus be filtered by the second purification module 800 .
  • the cooling liquid in the mixing tank 710 is stirred and discharged to the static tank 720.
  • the static tank 720 can keep the cooling liquid, which is beneficial to the further precipitation of air bubbles in the cooling liquid and reduces the proportion of air bubbles in the cooling liquid.
  • At least one circular orifice plate 740 and multiple half-moon orifice plates are arranged in the static tank 720 , as shown in FIG. 10 .
  • the size of the circular orifice plate 740 is the same as the cross-sectional area of the static box, and the circular orifice plate 740 and the half-moon-shaped orifice plate are provided with a plurality of flow holes 741 .
  • the circular orifice 740 is arranged in the static box 720 and near the side of the mixing box 710, and the half-moon orifice is arranged on the lower side of the circular orifice 740, and the circular orifice 740 and the half-moon can be welded together.
  • the orifice plates are respectively welded on the inner wall of the static box 720 . That is to say, when the cooling liquid in the mixing tank 710 flows into the static tank 720 , it needs to pass through the circular orifice plate 740 and the half-moon-shaped orifice plate in the static tank 720 first. After the cooling liquid flows through the circular orifice plate 740, the flow rate of the cooling liquid decreases.
  • the half-moon-shaped orifice plate can further suppress the flow velocity of the cooling liquid, thereby facilitating the floating and precipitation of air bubbles in the cooling liquid.
  • an air injection device 730 is provided in the mixing box 710 , and the air injection device 730 communicates with the aeration inlet of the mixing box 710 .
  • the air injection device 730 comprises a plurality of sets of concentric annular pipes 731, a connecting pipe 732 connecting multiple sets of annular pipes 731 and an air intake main pipe 733 communicated with the communicating pipe 732, the air intake main pipe 733 and the aeration pipe 710 of the mixing box 710
  • the gas inlets are connected, and each annular tube 731 is provided with a plurality of nozzles 7311 .
  • the ring diameter difference of two adjacent ring tubes is in the range of 5cm to 10cm.
  • the aperture of each nozzle 7311 can be designed to be about 1 cm, and the distance between two adjacent nozzles 7311 is in the range of 5 cm to 10 cm.
  • the mixing tank 710 communicates with the static tank 720 through a transfer line 760 .
  • a pressure balance line 770 is also provided between the mixing box 710 and the resting box 720 .
  • a plurality of pressure sensors 711 can also be provided inside the mixing box 710, and the pressure sensors 711 can calculate the coolant level in the mixing box 710 according to the pressure in the mixing box 710, and the pressure sensors 711 are electrically connected to the main control room.
  • the static tank 720 communicates with the nuclear reactor through an upflush pipeline 780 .
  • the upstroke pipeline 780 is provided with an upstroke pump 781 and an upstroke flow control valve 782 .
  • the downflow flow control valve 751 is opened, the upstroke flow control valve 782 is opened, and the upstroke pump 781 starts to work.
  • the cooling liquid in the nuclear reactor enters the mixing tank 710 along the drain line 750, and the second purification module 800 aerates the mixing tank 710 along the aeration inlet of the mixing tank 710, so that the cooling liquid in the mixing tank 710 is fully mixed.
  • the radioactive elements contained in the cooling liquid in the mixing box 710 enter the second purification module 800 along the aeration outlet of the mixing box 710 .
  • the cooling liquid in the mixing tank 710 enters the static tank 720 along the transfer line 760, and the circular orifice plate 740 and the half-moon-shaped orifice plate in the static tank 720 can block the cooling liquid and make the bubbles in the cooling liquid separate out.
  • the coolant in the storage tank 720 flows back to the nuclear reactor along the flushing pipeline 780 .
  • the inlet of a circulation line 830 communicates.
  • the filter device 810 may include multiple sets of filters connected in series, and an isolation valve 811 may be provided at the inlet of the filter device 810 and the outlet of the filter device 810 to control air flow into or out of the filter device 810 .
  • the first circulation line 830 is provided with a gas compression pump 831, the outlet of the first circulation line 830 communicates with the aeration inlet of the mixing box 710 through the second circulation line 840, communicates with the gas recovery box 860 through the gas return line 850, and the gas The recovery tank 860 supplies gas to the first circulation line 830 through the gas supplement line 870 .
  • a first flow control valve 871 can be set on the gas supply line 870, a second flow control valve 832 can be set near the entrance of the first circulation line 830; a third flow control valve 841 can be set on the second circulation line 840; the gas return line 850 A fourth flow control valve 851 may be provided on the top.
  • the gas compression pump 831 starts to work, and the gas in the first circulation line 830 may come from the gas recovery box 860 or the gas filtered in the filter device 810 .
  • the gas compression pump 831 can ventilate to the aeration inlet of the mixing box 710 through the second circulation pipeline 840, and can also enter the gas recovery box 860 through the gas return line 850.
  • the cooling liquid in the mixing box 710 contains The radioactive elements are released and enter the filter device 810 through the purification pipeline 820 along the aeration outlet of the mixing box 710 .
  • the fourth flow control valve 851 can be closed and the first flow control valve 871 can be opened, that is, the gas recovery box 860 can supply gas to the gas compression pump 831 of the first circulation line 830 .
  • the second purification module 800 also includes a connection between the nuclear reaction device and the inlet of the filter device 810
  • the air chamber down discharge pipe 880, and the air chamber down discharge pipe 880 can be provided with an air chamber down discharge isolation valve 881; an air chamber flush pipe 890 is also provided between the outlet of the first circulation pipeline 830 and the nuclear reactor.
  • a fifth flow control valve 891 may be provided on the upper flushing pipe 890 of the air chamber.
  • the air chamber compressor pump starts to work, and the air flow entering the first circulation pipeline 830 flows in three ways: the first way enters the gas recovery box 860 along the gas return line 850, that is, the gas flows to the gas recovery box 860 is used to supply air to the air chamber compressor pump in the later stage.
  • the fourth flow control valve 851 can be closed and the first flow control valve 871 on the gas supply line 870 can be opened, that is, the gas supply line 870 can transfer the gas flow in the gas recovery box 860 Supplement to the first circulation line 830; the second path enters the mixing box 710 along the second circulation line 840, and the gas in the mixing box 710 is discharged to the filter device 810 along the purification line 820; the third path enters along the upper flushing pipe 890 of the air chamber Go to the nuclear reactor and flush the nuclear reactor.
  • the radioactive elements in the cooling liquid in the nuclear reactor can be better purified, so that the radioactive elements in the nuclear reactor can be kept at a low level.

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Abstract

一种核反应装置及净化系统。核反应装置包括：反应容器（100），设置有反应腔（110）和封闭该反应腔（110）的顶盖（120）；反应模块（200），设置在反应腔（110）内，反应模块（200）在反应腔（110）内反应并释放热量；换热模块（300），设置在反应腔（110）内，换热模块（300）能够吸收反应模块（200）释放的热量，换热模块（300）的入口用于与供液系统连通，换热模块（300）的出口用于与热驱动系统连通。

Description

核反应装置及净化系统
相关申请的交叉引用
本申请要求于2021年11月05日提交中国专利局、申请号为202111308612.3、发明名称为“核反应装置及净化系统”的中国专利申请的优先权，其全部内容通过引用结合在本申请中。
技术领域
本申请涉及核反应技术领域，特别是核反应装置及净化系统。
技术背景
在核反应应用中需要考虑到至少两个方面的问题：换热问题和放射性元素的危害。现有的核反应堆多采用外置换热的方式，也即反应堆与换热模块分开设置，这导致反应堆的整个设计体积较大，不符合反应堆的小型化设计思路，另外外置换热的方式也存在换热利用率降低的问题；另一方面，由于核反应堆的冷却液中存在放射性元素，因此需要维持冷却液中的放射性元素在较低水平以降低对工作人员的伤害，同时提高反应堆的安全性。
发明内容
根据本申请的各种示例性实施例，有必要针对现有的核反应堆中换热模块外置的问题，提供一种核反应装置和包括该核反应装置的净化系统。
一种核反应装置，包括：
反应容器，设置有反应腔和封闭所述反应腔的顶盖；
反应模块，设置在所述反应腔内，所述反应模块在所述反应腔内反应并释放热量；
换热模块，设置在所述反应腔内，所述换热模块能够吸收所述反应模块释放热量，所述换热模块的入口用于与供液系统连通，所述换热模块的出口用于与热驱动系统连通。
上述核反应装置，将换热模块收容在反应容器的反应腔内以利用反应容器的内部空间，使得核反应装置的整体体积更小，更符合核反应装置小型化的设计方案。反应模块可 以为核反应模块，核反应模块反应过程中释放热量，由于换热模块和反应模块均位于反应腔内，为此反应模块释放的热量可以直接被换热模块吸收，吸收率高，如此相比外置式的换热模块而言，本核反应装置还能够提高对反应模块的换热利用率。
在其中一个实施例中，所述换热模块包括至少一套换热管束，每套所述换热管束的入口用于与所述供液系统连通，每套所述换热管束的出口用于与所述热驱动系统连通。
在其中一个实施例中，所述换热管束螺旋缠绕在所述反应模块的外壁。
在其中一个实施例中，多套所述换热管束沿所述反应模块的外壁周向布置。
在其中一个实施例中，所述核反应装置还包括定位板，所述定位板固定设置在所述反应模块外壁，所述定位板设置有与所述换热管束数量相同的定位孔，以分别固定多套所述换热管束。
在其中一个实施例中，所述核反应装置还包括固定组件，所述固定组件设置在所述顶盖，所述反应模块位于所述固定组件内，所述固定组件固定所述定位板，所述换热管束设置于所述固定组件的外壁。
在其中一个实施例中，所述固定组件包括吊篮和法兰盘，所述法兰盘将所述吊篮固定在所述顶盖，所述反应模块位于所述吊篮内，所述吊篮的外壁设置有连接件以固定所述定位板，所述换热管束设置所述吊篮的外壁。
在其中一个实施例中，所述反应腔内填充有冷却液，所述吊篮远离所述顶盖的一侧设置有下封头，所述下封头设置第一配流孔，所述第一配流孔连通所述反应腔与所述吊篮；
所述核反应装置还包括冷却液循环模块，所述冷却液模块将所述反应容器的所述冷却液驱动至所述定位板，所述定位板设置多个以供所述冷却液流过的第二配流孔。
在其中一个实施例中，所述反应模块包括设置在所述吊篮内的堆芯、与所述堆芯反应的控制棒组件以及驱动所述控制棒组件移动的驱动机构。
一种净化系统，包括所述的核反应装置，所述净化系统还包括第一净化模块和第二净化模块；
所述第一净化模块与所述核反应装置连通，并用于收容和循环所述核反应装置的所述冷却液；
所述第二净化模块与所述第一净化模块循环连通，所述第二净化模块向所述第一净化 模块曝气并净化所述第一净化模块内的流体。
在其中一个实施例中，所述第一净化模块包括相连通的搅混箱和静置箱；
所述搅混箱和所述静置箱分别与所述核反应装置连通，所述核反应装置的所述冷却液能够流入至所述搅混箱并从所述静置箱流入至所述核反应装置；所述搅混箱的曝气入口和曝气出口分别与所述第二净化模块连通。
在其中一个实施例中，所述搅混箱内有喷气装置，所述喷气装置与所述搅混箱的所述曝气入口连通。
在其中一个实施例中，所述喷气装置包括多套同心设置的圆环管、连接所述多套圆环管的连通管以及与所述连通管连通的进气母管，所述进气母管与所述搅混箱的所述曝气入口连通，每根所述圆环管均设置有多个喷嘴。
在其中一个实施例中，所述静置箱的形状为两端为半球形中间为圆柱形的箱体。
在其中一个实施例中，所述静置箱内设置有至少一块圆形孔板和多块半月形孔板。
在其中一个实施例中，所述第二净化模块包括至少一组过滤装置。
在其中一个实施例中，所述第一净化模块还包括下泄管线，所述下泄管线连通所述核反应装置和所述搅混箱；所述搅混箱与所述静置箱之间设置有转移管线和平衡管线；所述静置箱与所述核反应装置之间通过上冲管线连通，所述上冲管线设置有上冲泵。
在其中一个实施例中，所述搅混箱内设置有压力传感器，所述压力传感器能够根据所述搅混箱内的压力计算所述搅混箱的液位，所述压力传感器与主控室电性连接。
在其中一个实施例中，所述第二净化模块还包括连通所述搅混箱的所述曝气出口与所述过滤装置入口的净化管线，所述过滤装置的出口与第一循环管线的入口连通；
所述第一循环管线设置有气体压缩泵，所述第一循环管线的出口分别通过第二循环管线与所述搅混箱的曝气入口连通，通过气体回流管线与气体回收箱连通，所述气体回收箱通过气体补充管线向所述第一循环管线补气。
在其中一个实施例中，所述第二净化模块还包括连通所述核反应装置与所述过滤装置入口的气腔下泄管；所述第一循环管线的出口与所述核反应装置之间还设置有气腔上冲管。
附图说明
为了更清楚地说明本申请实施例或传统技术中的技术方案，下面将对实施例或传统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申请的一些实施例，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为本申请一实施例中的核反应装置的结构示意图；
图2为本申请一实施例中换热模块的结构示意图；
图3为本申请另一实施例中换热模块的结构示意图；
图4为本申请一实施例中定位板的结构示意图；
图5为本申请另一实施例中的核反应装置的结构示意图；
图6为本申请一实施例中的吊篮结构示意图；
图7为本申请一实施例中导流组件的结构示意图；
图8为图7中导流组件的俯视图；
图9为本申请一实施例中的净化系统的示意图；
图10为本申请一实施例中的圆形孔板的结构示意图；
图11为本申请一实施例中的喷气装置结构示意图；
图12为图11中喷气装置的另一方向示意图；及
图13为本申请另一实施例中的净化系统的示意图。
附图标号说明：
100、反应容器；110、反应腔；120、顶盖；130、隔离箱；131、隔离板；
200、反应模块；210、堆芯；220、控制棒组件；230、驱动机构；
300、换热模块；310、换热管束；320、导流组件；321、阻流板；
3211、收容孔；322、导流筒；3221、收容腔；
400、定位板；410、定位孔；420、第二配流孔；
500、固定组件；510、吊篮；511、连接件；520、法兰盘；530、下封头；
531、第一配流孔；600、冷却液循环模块；
700、第一净化模块；710、搅混箱；711、压力传感器；720、静置箱；
730、喷气装置；731、圆环管；
7311、喷嘴；732、连通管；733、进气母管；740、圆形孔板；
741、流通孔；750、下泄管线；751、下泄流量控制阀；760、转移管线；
770、平衡管线；
780、上冲管线；781、上冲泵；782、上冲流量控制阀；
800、第二净化模块；810、过滤装置；811、隔离阀；820、净化管线；
830、第一循环管线；831、气体压缩泵；832、第二流量控制阀；
840、第二循环管线；841、第三流量控制阀；
850、气体回流管线；851、第四流量控制阀；860、气体回收箱；
870、气体补充管线；871、第一流量控制阀；
880、气腔下泄管；881、气腔下泄隔离阀；890、气腔上冲管；
891、第五流量控制阀。
具体实施方式
为使本申请的上述目的、特征和优点能够更加明显易懂，下面结合附图对本申请的具体实施方式做详细的说明。在下面的描述中阐述了很多具体细节以便于充分理解本申请。但是本申请能够以很多不同于在此描述的其它方式来实施，本领域技术人员可以在不违背本申请内涵的情况下做类似改进，因此本申请不受下面公开的具体实施例的限制。
在本申请的描述中，需要理解的是，术语“中心”、“纵向”、“横向”、“长度”、“宽度”、“厚度”、“上”、“下”、“前”、“后”、“左”、“右”、“竖直”、“水平”、“顶”、“底”、“内”、“外”、“顺时针”、“逆时针”、“轴向”、“径向”、“周向”等指示的方位或位置关系为基于附图所示的方位或位置关系，仅是为了便于描述本申请和简化描述，而不是指示或暗示所指的装置或元件必须具有特定的方位、以特定的方位构造和操作，因此不能理解为对本申请的限制。
此外，术语“第一”、“第二”仅用于描述目的，而不能理解为指示或暗示相对重要性或者隐含指明所指示的技术特征的数量。由此，限定有“第一”、“第二”的特征可以明示或者隐含地包括至少一个该特征。在本申请的描述中，“多个”的含义是至少两个，例如 两个，三个等，除非另有明确具体的限定。
在本申请中，除非另有明确的规定和限定，术语“安装”、“相连”、“连接”、“固定”等术语应做广义理解，例如，可以是固定连接，也可以是可拆卸连接，或成一体；可以是机械连接，也可以是电连接；可以是直接相连，也可以通过中间媒介间接相连，可以是两个元件内部的连通或两个元件的相互作用关系，除非另有明确的限定。对于本领域的普通技术人员而言，可以根据具体情况理解上述术语在本申请中的具体含义。
在本申请中，除非另有明确的规定和限定，第一特征在第二特征“上”或“下”可以是第一和第二特征直接接触，或第一和第二特征通过中间媒介间接接触。而且，第一特征在第二特征“之上”、“上方”和“上面”可是第一特征在第二特征正上方或斜上方，或仅仅表示第一特征水平高度高于第二特征。第一特征在第二特征“之下”、“下方”和“下面”可以是第一特征在第二特征正下方或斜下方，或仅仅表示第一特征水平高度小于第二特征。
需要说明的是，当元件被称为“固定于”或“设置于”另一个元件，它可以直接在另一个元件上或者也可以存在居中的元件。当一个元件被认为是“连接”另一个元件，它可以是直接连接到另一个元件或者可能同时存在居中元件。本文所使用的术语“垂直的”、“水平的”、“上”、“下”、“左”、“右”以及类似的表述只是为了说明的目的，并不表示是唯一的实施方式。
核反应装置能够将化学能或者将核能等转化为热量以用来驱动相关的热驱动系统，例如核反应装置将放出的热量将水汽化以此驱动涡轮机工作。核反应装置用作核反应时需要注意至少两个方便的问题，现有的核反应堆多采用外置换热的方式，也即反应堆与换热模块分开设置，这导致反应堆的整个设计体积较大，不符合反应堆的小型化设计思路，另外外置换热的方式也存在换热利用率降低的问题；另一方面，由于核反应堆的冷却液中存在放射性元素，因此需要维持冷却液中的放射性元素在较低水平以降低对工作人员的伤害。为此研发人员提出一种核反应装置，将反应模块和换热模块均收容在核反应装置内，以降低核反应装置的整体体积。另外，本申请还提出一种净化系统，对核反应装置在反应过程中可能存在的污染元素或有害元素等进行净化，以降低污染并保障工作人员的安全以及反应堆运行的安全。
本申请提出的核反应装置，可以利用于核反应堆过程，但不限与此，例如还可以化学放热的过程也可以通过本申请中的核反应装置完成。
参阅图1，图1示出了本申请一实施例中的核反应装置的结构示意图，本申请一实施例提供了的核反应装置，包括：反应容器100、反应模块200和换热模块300，反应容器100用于收容反应模块200和换热模块300，如此使得整个核反应装置的空间占比更小，更符合核反应装置小型化的设计需求。另外，反应模块200放出的热量可以直接被换热模块300利用，如此相比外置式的换热模块300而言，本实施例中的核反应装置还可以提高换热利用率。反应模块200可以是核反应堆，例如可以包括堆芯、控制棒组件以及驱动控制棒组件的驱动机构；反应模块200还可以是包括化学元素反应放热的模块。换热模块300主要是吸收反应模块200在反应过程中放出的热量以此便于其它驱动工作，例如换热模块300的入口用于与供液系统连通，换热模块300吸热后能够将供液系统传送过来的水源汽化以此来推动热驱动系统，例如推动涡轮机。
具体地，反应容器100设置有反应腔110和封闭反应腔110的顶盖120，如此使得反应容器100为相对封闭的空间，顶盖120一方面能够防止反应容器100的温度散失；另一方面也能够防止反应容器100内污染元素或者放射性元素扩散。反应模块200设置在反应腔110内，反应模块200在反应腔110内反应并释放热量；换热模块300设置在反应腔110内，换热模块300能够吸收反应模块200释放热量，换热模块300的入口用于与供液系统连通，换热模块300的出口用于与热驱动系统连通。换热模块300可以包括至少一套换热管束310，每根换热管束310的入口与供液系统连通，每套换热管束310的出口用于与热驱动系统连通。
在本实施例中，反应模块200工作时放出热量，换热模块300吸收反应模块200的热量后能够将供液系统中输送至换热模块300的水汽化，并推动热驱动系统工作。由于将换热模块300收容在反应腔110内，因此使得核反应装置的整体体积更小，更符合核反应装置小型化的设计方案。反应模块200可以为核反应模块200，核反应模块200反应过程中释放热量，由于换热模块300和反应模块200均位于反应容器100内，为此反应模块200释放的热量可以直接被换热模块300吸收，吸热率高，如此相比外置式的换热模块300而言，本核反应装置还能够提高对反应模块200的换热利用率。
为了提高换热模块300的利用率，发明人想到需要将换热模块300尽可能地靠近反应模块200，也就是通过缩短换热模块300与反应模块200之间的间距，以此尽可能地提高换热模块300的利用率。为此发明人将换热模块300内包括的换热管束310螺旋缠绕在反应模块200的外壁，参阅图2所示。由于换热模块300中的换热管束310螺旋缠绕在反应模块200的外壁，因此换热模块300中的换热管束310与反应模块200的外壁具有较大的接触面积，进而能够使得换热管束310更好地吸收反应模块200的热量。另外供液系统供给的水流可以从换热管束310的下部进入，然后从换热管束310的上部流出，在本实施例中，换热管束310的下部指的是靠近反应容器100底壁的一侧，换热管束310的上部指的是靠近顶盖120的一侧。这样设计的好处是能够缩短水流在换热管束310内的流动距离，也便于将汽化后的水蒸气直接排出。
在另一实施例中，参阅图5所示，参阅发明人采用多套换热管束310沿反应模块200的外壁周向布置。这一方案相比上一方案的不同点在于，换热管束310采用靠近反应模块200的外壁设置。换热管束310的螺旋半径小于反应容器100与反应模块200之间的距离。本实施例中方案与上一实施例中的设计方案可以根据反应容器100的反应腔110的体积等选择设计。
发明人发现，当多套换热管束310设置在反应模块200的外壁周向时，由于换热管束310缺少定位构件，因此较难使得换热管束310的位置固定。为此发明人想到在核反应装置内设置定位板400，通过在定位板400上设置定位孔410以此实现对换热管束310的固定。具体地，参阅图4和图5所示，核反应装置还包括定位板400，其中定位板400固定设置在反应模块200外壁，定位板400设置有与换热管束310数量相同的定位孔410，以分别固定多个换热管束310。如此，当定位板400的位置与反应模块200的位置固定后，能够通过自身的定位孔410来固定换热管束310。
当反应模块200和换热模块300分别设置在反应容器100内后，为了避免反应模块200在反应过程中与换热模块300之间产生相对移动，以此影响反应模块200和换热模块300的工作过程。为此，通过固定组件500固定反应模块200。具体地，参阅图5所示，核反应装置还包括固定组件500，其中固定组件500设置在顶盖120，反应模块200位于固定组件500内，固定组件500固定定位板400，换热管束310设置于固定组件500的外 壁。通过固定组件500固定反应模块200能够保证反应模块200能够在在反应容器100内的位置稳定，进一步地使得反应模块200和换热模块300能够正常工作。由于固定组件500用于收容反应模块200，为此可以将换热模块300中的换热管束310缠绕设置在固定组件500的外壁或者周向设置在固定组件500的外壁。
进一步地，参阅图5和图6所示，固定组件500包括吊篮510和法兰盘520，其中法兰盘520将吊篮510固定在顶盖120，反应模块200位于吊篮510内，吊篮510的外壁设置有连接件511以固定定位板400，连接件511可以为卡扣，换热管束310设置吊篮510的外壁，参阅图3所示。在本实施例中，通过法兰盘520能够较好地将吊篮510固定在顶盖120上，吊篮510的底部可以被反应容器100的底壁支撑。另外，为了便于换热管束310的布置，法兰盘520与吊篮510连接的一端设置在吊篮510内。
发明人在使用核反应装置的过程中，为了更好地吸收反应模块200的热量，例如反应模块200为核反应时，需要向反应容器100内通入冷却液，以将反应模块200中反应的热量带出，其中冷却液可以采用铅铋合金等，为了使得冷却液能够在反应容器100内循环流动以及更加均匀地流入核反应装置进而带走核反应装置释放的热量，为此在发明人想到在设置冷却液循环模块600以及在反应容器100内设置下封头530。具体地，参阅图5所示，反应容器100的反应腔110内填充有冷却液，吊篮510远离顶盖120的一侧设置有下封头530，例如下封头530可以采用卡接的方式与吊篮510固定或者被吊篮510支撑，其中下封头530设置第一配流孔531，第一配流孔531连通反应容器100的反应腔110与吊篮510。冷却液能够从第一配流孔531进入到吊篮510内；核反应装置还包括冷却液循环模块600，冷却液模块将反应容器100的冷却液驱动至定位板400，定位板400设置多个以供冷却液流过的第二配流孔420。冷却液循环模块600的数量可以为多个。
在本实施例中，冷却液循环模块600能够将反应容器100内的冷却液驱动至定位板400，由于冷却液吸收了反应模块200的热量，因此冷却液驱动至定位板400时能够将热量传递给定位板400下方的换热管束310。而在定位板400上设置第二配流孔420，能够使得定位板400的冷却液流速更加均匀，使得冷却液能够更好地与换热管束310进行热交换。当冷却液从定位板400从换热管束310流过进入到下封头530后，冷却液能够从下封头530的第一配流孔531再进入到吊篮510内以再次吸收反应模块200的热量。在本实施 例中，对冷却液循环系统进行举例说明，冷却液循环系统包括泵以及输送管路，泵设置在输送管路上，输送管路与反应容器100的反应腔110连通。泵工作时，能够将冷却液抽入至输送管路，并驱动流向至定位板400。为了减少输送管路与反应容器100之间的开口设置，输送管路可以采用双层管路，即通过在反应容器100上设置一个开口，能够完成冷却液进入到输送管路以及从输送管路排出。
当换热管束310设置在吊篮510外壁的周向时，相邻两个换热管束310可能存在间隙，当冷却液流向换热管束310时，可能会从换热管束310之间的间隙流过，如此不利于冷却液的热量传递给换热管束310。为此，发明人想到，设置导流组件320来收容换热管束310，进而避免冷却液从换热管束310之间的间隙流过。具体地，参阅图7和图8所示，导流组件320包括相对设置的阻流板321以及位于阻流板321之间的导流筒322，导流筒322和阻流板321套设在吊篮510的外壁，导流筒322设置有多个收容腔3221以收容换热管束，阻流板321上设置有与收容腔3221连通的收容孔3211使得换热管束310能够进入到导流筒322的收容腔3221。在本实施例中，导流筒322和阻流板321上可以通过设置通孔套设在吊篮510的外壁，将换热管束310放置在导流筒322的收容腔3221内，冷却液流向换热管束310时从导流筒322的收容腔3221内流过，如此冷却液能够将热量更充分地传递至换热管束310，从而进一步地提高换热管束地吸热效率。
一实施例中，顶盖120远离反应容器100的一侧设置有隔离箱130，参阅图5所示，隔离箱130内设置有隔离板131以将隔离箱130分隔为给水环箱以及蒸气环箱。其中给水环箱连通供液系统和换热模块300的入口，蒸气环箱连通热驱动系统和换热模块300的出口。隔离箱130能够较好地起到缓冲水流和气流的作用。
一实施例中，参阅图5所示，当核反应装置用于核反应过程时，反应模块200包括设置在吊篮510内的堆芯210、与堆芯210反应的控制棒组件220以及驱动控制棒组件220移动的驱动机构230。反应模块200的反应过程为，驱动机构230驱动控制棒组件220移动使得控制棒组件220与堆芯210反应并放出热量。
本实施例的工作原理为，驱动机构230驱动控制棒组件220移动，进而控制堆芯210进行核反应放热的功率。供液系统通过隔离箱130向换热模块300的换热管束310输送水流，反应容器100内填充有冷却液，冷却液能够吸收堆芯210核反应放出的热量，冷却液 循环模块600将冷却液驱动至定位板400，进一步地通过定位板400上的第二配流孔420与换热模块300使得换热模块300的换热管束310内的水流吸收热量汽化，换热管束310的水流汽化后推动热驱动系统。同时，冷却液能够从下封头530的第一配流孔531流入至堆芯210内再次吸收堆芯210的热量。
在本实施例中，由于换热模块300内置，因此减小了整个核反应装置的体积，符合核反应装置小型化的设计思路。另外，由于换热模块300中的换热管束310采用螺旋缠绕在吊篮510的外壁或者周向布置在吊篮510的外壁，因此能够较好地吸收核反应过程中的热量。此外，定位板400板上的第二配流孔420使得定位板400下方的冷却液流速更加均匀，如此也能够提高换热管束310的吸热效率。最后下封头530上设置的第一配流孔531能够使得冷却液进入或者流出时的更加均匀。
考虑核反应装置在反应过程中可能会释放出污染元素或者放射性元素，为此需要对这些元素净化处理。当核反应装置应用在核反应过程时，由于冷却液中包含放射性元素，如果不维持冷却液中的放射性元素在较低水平，则可能会危害操作人员的安全，另外也会影响核反应过程。为此，发明人想到设置一种在线净化系统，以能够自动地吸收核反应中冷却液中的放射性元素。本申请的思路是，设计两个净化模块，分别为第一净化模块700和第二净化模块800，第一净化模块700用于收容冷却液，第二净化模块800用于向第一净化模块700内曝气，进而使得第一净化模块700内的冷却液搅拌释放冷却液中的包含的放射性元素，第一净化模块700内释放的放射性元素能够随气流进入到第二净化模块800内，并被第二净化模块800净化。需要说明的是，第二净化模块800向第一净化模块700曝气的气体可以是氦气、二氧化碳或氮气等，还可以是这些气体的混合物。
具体地，参阅图9所示，净化系统还包括第一净化模块700和第二净化模块800。其中，第一净化模块700与核反应装置连通，并用于收容和循环核反应装置的冷却液；第二净化模块800与第一净化模块700循环连通，第二净化模块800向第一净化模块700曝气并净化第一净化模块700内的流体。
在本实施例中，核反应装置的冷却液能够进入到第一净化模块700，第二净化模块800向第一净化模块700内曝气，使得第一净化模块700收容的冷却液搅拌，进而使得冷却液中释放更多的放射性元素。冷却液中释放的放射性元素能够进入到第二净化模块800内， 并被第二净化模块800净化。需要说明的是，第一净化模块700和第二净化模块800之间可以设置至少两个连通管732路，其中一个连通管732路用于第二净化模块800向第一净化模块700曝气，另一连通管732路用于第一净化模块700中的气流进入到第二净化模块800。另外，第二净化模块800可以包括至少一组过滤装置810。
在本实施例中，通过第一净化模块700和第二净化模块800能够使得核反应装置的放射性元素维持在较低水平，能够降低核反应装置对工作人员的辐射影响，另外也能够使得核反应装置能够较好地运行。
进一步地，参阅图9所述，第一净化模块700包括相连通的搅混箱710和静置箱720。其中搅混箱710和静置箱720分别与核反应装置连通，核反应装置的冷却液能够流入至搅混箱710并从静置箱720流入至核反应装置；搅混箱710的曝气入口和曝气出口分别与第二净化模块800连通，第二净化模块800向搅混箱710内曝气，并净化搅混箱710内排出的气流。
在本实施例中，冷却液先进入至搅混箱710内，然后第二净化模块800通过搅混箱710的曝气入口向搅混箱710内曝气，使得搅混箱710中的冷却液能够被充分搅拌，此时冷却液中包含的放射性元素随气流能够从搅混箱710的曝气出口进入到第二净化模块800内，从而被第二净化模块800过滤。搅混箱710的冷却液被搅拌后排放至静置箱720，静置箱720能够静置冷却液，利于冷却液中的气泡进一步析出，降低冷却液中的气泡份额。
另外为了使得静置箱720能够较好地静置冷却液，静置箱720内设置有至少一块圆形孔板740和多块半月形孔板，可参阅图10所示。圆形孔板740的尺寸与静置箱横截面积相同，圆形孔板740和半月形孔板设置多个流通孔741。其中圆形孔板740设置在静置箱720内且靠近搅混箱710的一侧，半月形孔板设置在圆形孔板740下侧，可以采用焊接的方式将圆形孔板740和半月形孔板分别焊接在静置箱720的内壁。也即是说，当搅混箱710内的冷却液流入至静置箱720时，需要先经过静置箱720内的圆形孔板740和半月形孔板。冷却液流经圆形孔板740后，冷却液的流速降低。而半月形孔板能够对冷却液的流速进行进一步地抑制，从而有利于冷却液内气泡上浮析出。
为了较好地向搅拌箱内曝气，一实施例中，参阅图11和图12所示，搅混箱710内设置有喷气装置730，喷气装置730与搅混箱710的曝气入口连通。其中喷气装置730包括 多套同心设置的圆环管731、连接多套圆环管731的连通管732以及与连通管732连通的进气母管733，进气母管733与搅混箱710的曝气入口连通，每根圆环管731均设置有多个喷嘴7311。相邻两个圆环管的圆环直径差异在5cm至10cm范围内。每个喷嘴7311的孔径可以设计为1cm左右，相邻两个喷嘴7311之间的间隔5cm至10cm范围内。
为了更好地呈现本申请中的第一净化模块700，参阅图13所示，第一净化模块700包括下泄管线750，其中下泄管线750连通核反应装置与搅混箱710，下泄管线750可以设置有下泄流量控制阀751。搅混箱710与静置箱720之间通过转移管线760连通。另外为了平衡搅混箱710与静置箱720内的气压，为此搅混箱710与静置箱720之间还设置有压力平衡管线770。搅混箱710的内部还可以设置多个压力传感器711，压力传感器711能够根据搅混箱710内的压力计算搅混箱710内的冷却液液位，压力传感器711与主控室电性连接。当主控室内显示的搅混箱710内冷却液液位较低时，此时可以调大下泄流量控制阀751，同时调小上冲流量控制阀782。静置箱720通过上冲管线780与核反应装置连通。上冲管线780上设置有上冲泵781和上冲流量控制阀782。
在本实施例中，在使用第一净化模块700时，将下泄流量控制阀751开启，上冲流量控制阀782开启，上冲泵781开始工作。核反应装置内的冷却液沿下泄管线750进入到搅混箱710，第二净化模块800沿搅混箱710的曝气入口向搅混箱710内曝气，使得搅混箱710的冷却液被充分搅混。搅混箱710内冷却液中包含的放射性元素沿搅混箱710的曝气出口进入到第二净化模块800。搅混箱710内的冷却液沿转移管线760进入到静置箱720，静置箱720内的圆形孔板740和半月形孔板能够阻挡冷却液，并使得冷却液中的气泡析出，位于静置箱720内的冷却液沿上冲管线780回流至核反应装置。
另外，为了更好地呈现第二净化模块800，参阅图13所示，第二净化模块800还包括连通搅混箱710曝气出口与过滤装置810入口的净化管线820，过滤装置810的出口与第一循环管线830的入口连通。过滤装置810可以包括多组串联的过滤器，过滤装置810的入口和过滤装置810的出口可以分别设置隔离阀811以控制气流进入过滤装置810或从过滤装置810排出。第一循环管线830上设置有气体压缩泵831，第一循环管线830的出口分别通过第二循环管线840与搅混箱710的曝气入口连通，通过气体回流管线850与气体回收箱860连通，气体回收箱860通过气体补充管线870向第一循环管线830补气。气 体补充管线870上可以设置第一流量控制阀871，靠近第一循环管线830的入口可以设置第二流量控制阀832；第二循环管线840上可以设置第三流量控制阀841；气体回流管线850上可以设置第四流量控制阀851。
在本实施例中，气体压缩泵831开始工作，第一循环管线830内的气体可以来自于气体回收箱860或者过滤装置810内过滤的气体。气体压缩泵831可以通过第二循环管线840向搅混箱710的曝气入口通气也可以通过气体回流管线850进入气体回收箱860，气体进入到搅混箱710后使得搅混箱710内的冷却液中包含的放射性元素释放并沿搅混箱710的曝气出口经净化管线820进入到过滤装置810。当气体压缩泵831的气流不足时，此时可以关闭第四流量控制阀851开启第一流量控制阀871，也即通过气体回收箱860向第一循环管线830的气体压缩泵831补气。
进一步地，为了利用第二净化模块800内的气流对核反应装置内进行清洗，从而带走制冷液中更多的放射性元素，为此第二净化模块800还包括连通核反应装置与过滤装置810入口的气腔下泄管880，气腔下泄管880上可以设置气腔下泄隔离阀881；第一循环管线830的出口与核反应装置之间还设置有气腔上冲管890。另外，气腔上冲管890上可以设置第五流量控制阀891。
当第二净化模块800工作时，气腔压缩泵开始工作，进入第一循环管线830的气流分三路流动：第一路沿气体回流管线850进入气体回收箱860，也即气体流向气体回收箱860以用于后期向气腔压缩泵补气。当第一循环管线830的气压不足时，此时可以关闭第四流量控制阀851开启气体补充管线870上的第一流量控制阀871，也即气体补充管线870能够将气体回收箱860内的气流补充至第一循环管线830；第二路沿第二循环管线840进入到搅混箱710，搅混箱710内的气体沿净化管线820排放至过滤装置810；第三路沿气腔上冲管890进入至核反应装置并对核反应装置进行冲刷。
通过本申请中提出的第一净化模块700和第二净化模块800能够较好地净化核反应装置中冷却液内的放射性元素，从而使得核反应装置内的放射性元素维持在较低水平。
以上实施例的各技术特征可以进行任意的组合，为使描述简洁，未对上述实施例中的各个技术特征所有可能的组合都进行描述，然而，只要这些技术特征的组合不存在矛盾，都应当认为是本说明书记载的范围。
以上实施例仅表达了本申请的几种实施方式，其描述较为具体和详细，但并不能因此而理解为对申请专利范围的限制。应当指出的是，对于本领域的普通技术人员来说，在不脱离本申请构思的前提下，还可以做出若干变形和改进，这些都属于本申请的保护范围。因此，本申请专利的保护范围应以所附权利要求为准。

Claims (20)

  1. 一种核反应装置，包括：
    反应容器，设置有反应腔和封闭所述反应腔的顶盖；
    反应模块，设置在所述反应腔内，所述反应模块在所述反应腔内反应并释放热量；及
    换热模块，设置在所述反应腔内，所述换热模块能够吸收所述反应模块释放热量，所述换热模块的入口用于与供液系统连通，所述换热模块的出口用于与热驱动系统连通。
  2. 根据权利要求1所述的核反应装置，其中，所述换热模块包括至少一套换热管束，每套所述换热管束的入口用于与所述供液系统连通，每套所述换热管束的出口用于与所述热驱动系统连通。
  3. 根据权利要求2所述的核反应装置，其中，所述换热管束螺旋缠绕在所述反应模块的外壁。
  4. 根据权利要求2所述的核反应装置，其中，多套所述换热管束沿所述反应模块的外壁周向布置。
  5. 根据权利要求4所述的核反应装置，其中，所述核反应装置还包括定位板，所述定位板固定设置在所述反应模块外壁，所述定位板设置有与所述换热管束数量相同的定位孔，以分别固定多套所述换热管束。
  6. 根据权利要求5所述的核反应装置，其中，所述核反应装置还包括固定组件，所述固定组件设置在所述顶盖，所述反应模块位于所述固定组件内，所述固定组件固定所述定位板，所述换热管束设置于所述固定组件的外壁。
  7. 根据权利要求6所述的核反应装置，其中，所述固定组件包括吊篮和法兰盘，所述法兰盘将所述吊篮固定在所述顶盖，所述反应模块位于所述吊篮内，所述吊篮的外壁设置有连接件以固定所述定位板，所述换热管束设置所述吊篮的外壁。
  8. 根据权利要求7所述的核反应装置，其中，所述反应腔内填充有冷却液，所述吊篮远离所述顶盖的一侧设置有下封头，所述下封头设置第一配流孔，所述第一配流孔连通所述反应腔与所述吊篮；
    所述核反应装置还包括冷却液循环模块，所述冷却液模块将所述反应容器的所述冷却液驱动至所述定位板，所述定位板设置多个以供所述冷却液流过的第二配流孔。
  9. 根据权利要求8所述的核反应装置，其中，所述反应模块包括设置在所述吊篮内的堆芯、与所述堆芯反应的控制棒组件以及驱动所述控制棒组件移动的驱动机构。
  10. 一种净化系统，包括权利要求1至9中任一项所述的核反应装置，所述净化系统还包括第一净化模块和第二净化模块；
    所述第一净化模块与所述核反应装置连通，并用于收容和循环所述核反应装置的所述冷却液；
    所述第二净化模块与所述第一净化模块循环连通，所述第二净化模块向所述第一净化模块曝气并净化所述第一净化模块内的流体。
  11. 根据权利要求10所述的净化系统，其中，所述第一净化模块包括相连通的搅混箱和静置箱；
    所述搅混箱和所述静置箱分别与所述核反应装置连通，所述核反应装置的所述冷却液能够流入至所述搅混箱并从所述静置箱流入至所述核反应装置；所述搅混箱的曝气入口和曝气出口分别与所述第二净化模块连通。
  12. 根据权利要求11所述的净化系统，其中，所述搅混箱内有喷气装置，所述喷气装置与所述搅混箱的所述曝气入口连通。
  13. 根据权利要求12所述的净化系统，其中，所述喷气装置包括多套同心设置的圆环管、连接所述多套圆环管的连通管以及与所述连通管连通的进气母管，所述进气母管与所述搅混箱的所述曝气入口连通，每根所述圆环管均设置有多个喷嘴。
  14. 根据权利要求11所述的净化系统，其中，所述静置箱的形状为两端为半球形中间为圆柱形的箱体。
  15. 根据权利要求11所述的净化系统，其中，所述静置箱内设置有至少一块圆形孔板和多块半月形孔板。
  16. 根据权利要求11所述的净化系统，其中，所述第二净化模块包括至少一组过滤装置。
  17. 根据权利要求11所述的净化系统，其中，所述第一净化模块还包括下泄管线，所述下泄管线连通所述核反应装置和所述搅混箱；所述搅混箱与所述静置箱之间设置有转移管线和平衡管线；所述静置箱与所述核反应装置之间通过上冲管线连通，所述上冲管线 设置有上冲泵。
  18. 根据权利要求17所述的净化系统，其中，所述搅混箱内设置有压力传感器，所述压力传感器能够根据所述搅混箱内的压力计算所述搅混箱的液位，所述压力传感器与主控室电性连接。
  19. 根据权利要求16所述的净化系统，其中，所述第二净化模块还包括连通所述搅混箱的所述曝气出口与所述过滤装置入口的净化管线，所述过滤装置的出口与第一循环管线的入口连通；
    所述第一循环管线设置有气体压缩泵，所述第一循环管线的出口分别通过第二循环管线与所述搅混箱的曝气入口连通，通过气体回流管线与气体回收箱连通，所述气体回收箱通过气体补充管线向所述第一循环管线补气。
  20. 根据权利要求19所述的净化系统，其中，所述第二净化模块还包括连通所述核反应装置与所述过滤装置入口的气腔下泄管；所述第一循环管线的出口与所述核反应装置之间还设置有气腔上冲管。
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