CN116525153A - Passive reactor core heat leading-out device, horizontal high-temperature gas cooled reactor and cooling method - Google Patents

Passive reactor core heat leading-out device, horizontal high-temperature gas cooled reactor and cooling method Download PDF

Info

Publication number
CN116525153A
CN116525153A CN202310281217.3A CN202310281217A CN116525153A CN 116525153 A CN116525153 A CN 116525153A CN 202310281217 A CN202310281217 A CN 202310281217A CN 116525153 A CN116525153 A CN 116525153A
Authority
CN
China
Prior art keywords
pipe section
cooling water
heat
reactor
water tank
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Pending
Application number
CN202310281217.3A
Other languages
Chinese (zh)
Inventor
黄政
董建华
张朔婷
张成龙
朱思阳
贺楷
王贺南
刘国明
陈巧艳
邹文重
于沛
李丽娟
堵树宏
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China Nuclear Power Engineering Co Ltd
Original Assignee
China Nuclear Power Engineering Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by China Nuclear Power Engineering Co Ltd filed Critical China Nuclear Power Engineering Co Ltd
Priority to CN202310281217.3A priority Critical patent/CN116525153A/en
Publication of CN116525153A publication Critical patent/CN116525153A/en
Pending legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18Emergency cooling arrangements; Removing shut-down heat
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

The invention discloses a passive reactor core heat leading-out device, a horizontal high-temperature gas cooled reactor and a cooling method. The device comprises: cooling water tank, circulation loop. The cooling water tank accommodates cooling water, and the position of the cooling water tank is higher than the position of the circulation loop. The circulation loop comprises an access pipe section and a return pipe section, and the access pipe section and the return pipe section are both connected with the cooling water tank. The circulation loop further comprises a plurality of heat absorption pipe sections, two ends of each heat absorption pipe section are connected with the access pipe section and the backflow pipe section respectively, the plurality of heat absorption pipe sections are sequentially arranged along the horizontal direction and extend along the vertical direction, each heat absorption pipe section comprises an arc-shaped section, and the arc-shaped section surrounds the periphery of the pressure vessel. The cooling water in the cooling water tank flows into the circulation loop from the connecting pipe section, absorbs the heat emitted by the pressure vessel through the heat absorbing pipe section, and finally flows back into the cooling water tank from the return pipe section. The heat guiding device can cool the reactor core of the air cooled reactor, and has higher cooling efficiency.

Description

Passive reactor core heat leading-out device, horizontal high-temperature gas cooled reactor and cooling method
Technical Field
The invention particularly relates to a passive reactor core heat leading-out device, a horizontal high-temperature gas cooled reactor and a cooling method of a pressure vessel of the horizontal gas cooled reactor.
Background
As one of the alternative technologies of the fourth generation advanced reactor, the high temperature gas cooled reactor (HTGR) has compact and simplified design, high inherent safety and wide application prospect. The gas-cooled micro-reactor is a miniaturized prismatic high-temperature gas-cooled reactor, helium is adopted as a cooling working medium, four layers of full ceramic coated particles (TRISO) are adopted as fuel, and graphite is adopted as a moderator and a reactor core structural material. When accidents such as lost flow and reactive introduction occur, the forced circulation flow of helium coolant in the reactor is terminated, and the cooling capacity of the reactor core fuel is lost. To mitigate the consequences of an accident, it is necessary to continuously and effectively conduct away the decay heat within the core; for predicted operational transients with shutdown failure, it is also desirable to derive fission heat release. Otherwise the temperature of the fuel assembly and other components in the stack will continue to rise, eventually leading to breakage of TRISO particles and significant release of the radioactive fission products when the temperature exceeds its structural limit.
In order to cope with the accident condition and ensure the structural integrity of the reactor core, a passive reactor core heat leading-out system is mostly adopted in the design of the high-temperature gas cooled reactor as an accident alleviation means. Representative designs include GT-MHR and MHTGR reactors from general atmospheric corporation of America, and SC-HTGR reactors from AREVA corporation of France.
The technical scheme of the conventional passive reactor core heat export system has certain defects: firstly, the existing design scheme mainly aims at a vertically placed reactor, adopts a thin and high-shaped placement mode, and ensures that enough cold and heat source height difference and a driving pressure head are obtained; and is not applicable to a horizontally placed reactor. Secondly, the heat exchanger and the circulation loop of part of the scheme are arranged on one side of the reactor, so that heat transfer is uneven, and the cooling effect of the side without the heat exchanger is relatively weak, and the side is possibly high in concrete. In addition, the heat exchange area between the existing circulation loop and the reactor pressure vessel is relatively small,
and the distance is far, so that the heat exchange efficiency is limited. In view of the above-mentioned shortcomings of the prior art, a more efficient passive core heat-dissipating device is needed to meet the safety requirements of high-temperature gas cooled reactors.
Disclosure of Invention
The invention aims to solve the technical problems in the prior art and provides a passive reactor core heat leading-out device, a horizontal high-temperature gas cooled reactor and a cooling method.
According to an embodiment of the first aspect of the present invention, there is provided an passive core heat removal device comprising: cooling water tank, circulation loop. The cooling water tank is used for containing cooling water, and the position of the cooling water tank is higher than the position of the circulation loop. The circulating loop comprises an access pipe section and a backflow pipe section, and the access pipe section and the backflow pipe section are both connected with the cooling water tank. The circulating loop further comprises a plurality of heat absorption pipe sections, two ends of each heat absorption pipe section are respectively connected with the access pipe section and the reflux pipe section, the plurality of heat absorption pipe sections are sequentially arranged in the horizontal direction and extend in the vertical direction, each heat absorption pipe section comprises an arc-shaped section, and the arc-shaped section surrounds the periphery of a pressure vessel which is horizontally arranged in the reactor. The cooling water in the cooling water tank flows into the circulation loop from the connecting pipe section, absorbs the heat emitted by the pressure container through the heat absorbing pipe section, and finally flows back into the cooling water tank from the return pipe section after absorbing the heat.
Preferably, the number of the circulation loops is two, and the heat absorption pipe sections of the two circulation loops are symmetrically arranged and are respectively positioned at the left side and the right side of the pressure vessel.
Preferably, the circulation loop further comprises a diverter tube segment. The diversion pipe section is connected with the access pipe section and is used for diverting the cooling water in the access pipe section. The split pipe section extends along the horizontal direction and is also communicated with the lower ends of the plurality of heat absorbing pipe sections, and the split pipe section is used for enabling the split cooling water to flow into the heat absorbing pipe sections.
Preferably, the circulation loop further comprises a confluence pipe section, and the confluence pipe section is located above the diversion pipe section. The converging pipe section extends along the horizontal direction and is communicated with the upper ends of the plurality of heat absorbing pipe sections, and cooling water in the plurality of heat absorbing pipe sections is converged into the converging pipe section. And the converging pipe section is also communicated with the backflow pipe section and is used for enabling the converged cooling water to flow back into the cooling water tank.
Preferably, the access pipe section of the circulation loop extends along the vertical direction, and the middle part of the access pipe section is provided with a control valve which is used for controlling the opening or closing of the access pipe section.
Preferably, each pipe section of the circulation loop is made of stainless steel materials.
Preferably, the pipe diameter of the access pipe section is smaller than the pipe diameter of the heat absorption pipe section.
Preferably, the distance between the arc-shaped section of the heat absorbing pipe section and the pressure vessel is 0.2-0.5 times the diameter length of the pressure vessel.
According to an embodiment of the second aspect of the present invention, a horizontal high temperature gas cooled reactor is provided, comprising a horizontal reactor and the passive core heat deriving device described above. The reactor includes a core and a pressure vessel, the core being housed within the pressure vessel. The passive reactor core heat leading-out device is used for cooling the pressure vessel.
Preferably, the passive core heat extraction device employs the passive core heat extraction device described in claim 5. The system also includes a control unit electrically connected to the control valve of the passive core heat removal device. And the control unit is used for sending an opening signal to the control valve when the reactor fails, so that the control valve is opened, and the heat absorption pipe section of the passive reactor core heat conduction device is used for cooling the pressure vessel.
According to an embodiment of the third aspect of the present invention, there is provided a method for cooling a pressure vessel of a horizontal high temperature gas cooled reactor, the method using the passive core heat extraction device described above, comprising the steps of: when the reactor fails, the control valve is opened to enable the cooling water in the cooling water tank to flow into the circulation loop from the access pipe section. The cooling water enters the heat absorption pipe section from the access pipe section, and the cooling water flowing through the heat absorption pipe section absorbs heat emitted by the pressure container. The cooling water after absorbing heat is returned to the cooling water tank by the return pipe section.
The position of the cooling water tank in the passive reactor core heat leading-out device is higher than that of the circulating loop, so that the cooling water enters the circulating loop under the action of gravity and sequentially passes through the inlet pipe section, the heat absorption pipe section and the reflux pipe section, and finally flows back to the cooling water tank. When the cooling water passes through the heat absorption pipe section, the cooling water can absorb heat emitted by the pressure container, so that the pressure container is cooled. The middle part of the heat absorption pipe section can be attached to the surface of the pressure vessel in a larger area through the arc-shaped section, so that a larger heat exchange area and coverage range are realized, and the heat absorption efficiency of the pressure vessel can be improved. Therefore, the passive reactor core heat leading-out device can cool down the reactor core of the gas cooled reactor and has higher cooling efficiency.
Drawings
FIG. 1 is a schematic diagram of a passive core heat removal device in accordance with some embodiments of the present invention;
FIG. 2 is a front view of an passive core heat removal device in some embodiments of the invention;
FIG. 3 is a side view of an passive core heat removal device in some embodiments of the invention.
In the figure: 1-cooling water tank, 2-access pipe section, 3-control valve, 4-split pipe section, 5-heat absorption pipe section, 6-converging pipe section, 7-pressure vessel, 8-reflux pipe section.
Detailed Description
The following description of the embodiments of the present invention will be made more apparent, and the embodiments described in detail, but not necessarily all, in connection with the accompanying drawings. All other embodiments, which can be made by those skilled in the art based on the embodiments of the invention without making any inventive effort, are intended to fall within the scope of the invention.
In the description of the present invention, it should be noted that, the terms "upper", "lower", "upstream", "downstream", and the like indicate an orientation or a positional relationship based on the orientation or the positional relationship shown in the drawings, and are merely for convenience and simplicity of description, and do not indicate or imply that the apparatus or element in question must be provided with a specific orientation, be configured and operated in a specific orientation, and thus should not be construed as limiting the present invention.
In the description of the present invention, the terms "first," "second," "third," and the like are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.
In the description of the present invention, it should be noted that, unless explicitly specified and limited otherwise, the terms "connected," "configured," "mounted," "secured," and the like are to be construed broadly and may be either fixedly connected or detachably connected, or integrally connected, for example; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the present invention can be understood by those skilled in the art according to the specific circumstances.
Referring to fig. 1 and 2, the present invention discloses a passive core heat deriving device, comprising: a cooling water tank 1 and a circulation circuit.
Wherein, the cooling water tank 1 is used for holding cooling water, and the position of cooling water tank 1 is higher than the position of circulation circuit. The circulation loop comprises an access pipe section 2 and a return pipe section 8, and the access pipe section 2 and the return pipe section 8 are connected with the cooling water tank 1. The circulation loop further comprises a plurality of heat absorption pipe sections 5, two ends of the heat absorption pipe sections 5 are respectively connected with the access pipe section 2 and the backflow pipe section 8, the plurality of heat absorption pipe sections 5 are sequentially arranged along the horizontal direction and extend along the vertical direction, the heat absorption pipe sections 5 comprise arc-shaped sections, the shapes of the arc-shaped sections are matched with the shapes of the pressure vessels, and the arc-shaped sections encircle the periphery of the pressure vessels 7 which are horizontally arranged in the reactor. The cooling water in the cooling water tank 1 flows into the circulation loop from the inlet pipe section 2, absorbs the heat emitted by the pressure vessel 7 through the heat absorbing pipe section 5, and finally flows back into the cooling water tank 1 from the return pipe section 8.
Specifically, the cooling water tank 1 and the circulation loop in the passive core heat removal device are uniformly distributed in the reactor chamber. The cooling water enters the circulation loop under the action of the gravity driving pressure head, and flows through the access pipe section 2, the heat absorption pipe section 5 and the reflux pipe section 8 in sequence, and finally flows back to the cooling water tank 1. Further, when the cooling water flows through the heat absorption pipe section 5, the side wall of the reactor pressure vessel 7 releases heat to the surroundings by means of convection, radiation and the like, and the cooling water flowing through the pipe section near the reactor pressure vessel 7 absorbs the heat transferred by the reactor pressure vessel 7 to cool down the same. Since the core is provided in the pressure vessel 7, the heat extraction device can cool down the core.
In addition, the cooling water can form natural circulation flow in the cooling water circulation loop in a passive mode under the action of the gravity driving pressure head. Therefore, the heat leading-out device can cool the reactor core by means of passive means, does not need to rely on a power supply and an active pump, simplifies the system and equipment, improves the inherent safety of the nuclear power plant and ensures the economical efficiency.
Therefore, the passive reactor core heat leading-out device can rapidly and effectively lead out and transfer the reactor core heat to the final hot trap under the working condition that the temperature of the reactor core is increased after an accident, cool down the reactor core, maintain the reactor core at a coolable safety level in a long-term stage, finally ensure the structural integrity of the reactor and alleviate the accident result.
Referring to fig. 1 and 2, in the present embodiment, the number of circulation circuits is two, and the heat absorbing pipe sections 5 of the two circulation circuits are symmetrically arranged and are respectively located at the left and right sides of the pressure vessel 7.
Specifically, in the conventional passive core heat removal device, the heat exchanger and the circulation circuit are both disposed on one side of the reactor, which may result in uneven heat transfer, and the cooling effect on the side where the heat exchanger is not disposed is relatively weak, which may result in a higher temperature on the side. The heat-conducting device can effectively improve the uniformity and symmetry of cooling heat exchange by arranging the circulating loops on the left side and the right side of the pressure vessel 7 respectively, overcomes the asymmetry of cooling of the reactor core in the prior art, and improves the cooling effect of the far-end weak side. The cooling of the molten scrap bed under accident conditions by passive means is independent of the safety level power supply and the active pump, simplifies the system and equipment, improves the inherent safety of the nuclear power plant and ensures the economical efficiency.
Further, as shown in fig. 3, the number of heat absorbing pipe sections 5 in each circulation loop is 6. In order to ensure the heat absorption efficiency of the heat absorption pipe sections 5, the distance between two adjacent heat absorption pipe sections 5 should be 0.8-1.2m. It is worth noting that the distance between two adjacent heat absorbing pipe sections 5 can be adjusted according to the actual heat exchange power requirements and the size of the arrangement space. Preferably, the distance between two adjacent heat absorbing pipe sections 5 is 0.8m.
If the distance between the arc-shaped section of the heat absorbing pipe section 5 and the pressure vessel 7 is too large, the heat absorbing effect of the cooling water is greatly reduced. Therefore, in the present embodiment, the distance between the arc-shaped section of the heat absorbing pipe section 5 and the pressure vessel 7 is 0.2 to 0.5 times the diameter length of the pressure vessel 7 to ensure that the cooling water can efficiently absorb the heat emitted from the pressure vessel 7. Preferably, the distance between the arc-shaped section and the pressure vessel 7 is 0.2 times the diameter length of the pressure vessel 7. It will of course be appreciated that the distance between the arcuate section of the heat absorbing pipe section 5 and the pressure vessel 7 can be adjusted according to the actual heat exchange power requirements and the size of the layout space.
As shown in fig. 2, taking the pressure vessel 7 with a diameter length of 3m as an example, the distance between the arc-shaped section and the pressure vessel 7 is 0.6m, at which distance the cooling water can efficiently absorb the heat emitted from the pressure vessel 7.
In this embodiment, the circulation loop further comprises a diverter tube section 4. The diversion pipe section 4 is connected with the access pipe section 2 and is used for diverting the cooling water in the access pipe section 2. The split pipe section 4 extends in the horizontal direction and is also communicated with the lower ends of the plurality of heat absorbing pipe sections 5 for the split cooling water to flow into the heat absorbing pipe sections 5. In addition, the circulation circuit comprises a converging pipe section 6, and the converging pipe section 6 is positioned above the diverging pipe section 4. The confluence pipe section 6 extends in a horizontal direction, which communicates with upper ends of the plurality of heat absorption pipe sections 5, and cooling water in the plurality of heat absorption pipe sections 5 is converged into the confluence pipe section 6. The converging pipe section 6 is also communicated with a return pipe section 8 for the cooling water after converging to flow back into the cooling water tank 1.
Further, the access pipe section 2 of the circulation loop extends in the vertical direction, and the middle part of the access pipe section 2 is provided with a control valve 3, and the control valve 3 is used for controlling the opening or closing of the access pipe section 2. The control valve is arranged at the access pipe section 2 of the cooling water circulation pipeline. The reactor is in a closed state during normal operation, and can be opened according to a reactor shutdown signal or an operator opening instruction under an accident condition, so that cooling water can flow through a cooling water circulation loop from the cooling water tank 1 by means of a gravity pressure head formed by a fluid density difference, and finally returns to the cooling water tank 1.
Specifically, the circulation loop of the heat conduction device is arranged in the reactor cavity, adopts water as fluid working medium, and is provided with two independent pipeline loops. Each row of circulation loops comprises an access pipe section 2, a diversion pipe section 4, a heat absorption pipe section 5, a confluence pipe and a backflow pipe section 8. The access pipe section 2 is arranged vertically, the upper end of the access pipe section is connected to the bottom of the cooling water tank 1, and the lower end of the access pipe section is connected with the diversion pipe section 4 positioned below. The split pipe section 4 is horizontally arranged below the reactor pressure vessel 7, one end of the split pipe section is connected with the access pipe section 2, and the middle horizontal part of the split pipe section is connected with a plurality of heat absorption pipe sections 5 which are connected in parallel.
The height difference between the cooling water tank 1 and the pressure vessel 7 is 1000-3000mm. Preferably, the height difference between the cooling water tank 1 and the pressure vessel 7 is 1500mm. The circulation loop forms a gravity driving pressure head by means of the height difference between the cooling water tank 1 and the pressure vessel 7, and the cooling water in the cooling water tank 1 enters the split pipe section 4 from the access pipeline under the action of the gravity pressure head and then is split into a plurality of heat absorption pipe sections 5 connected with the split pipe section, and the split pipe sections enter different heat absorption pipe sections 5 respectively. Specifically, the middle portion of the heat absorbing pipe section 5 is an arc-shaped section which is semi-circular in shape and compactly surrounds the cylindrical portion of the reactor pressure vessel 7. The curvature of the arc section is fitted to the cylindrical portion of the pressure vessel 7. The wall surface of the reactor pressure vessel 7 heats the cooling water flowing through the heat absorption pipe section 5 by means of convection and radiation. With the continuous flow of the cooling water, the pressure vessel 7 is cooled down. The cooling water in the heat absorption pipe section 5 absorbs heat to heat, so that the density difference of the cooling water in the access pipe section 2 and the heat absorption pipe section 5 can be generated, a driving pressure head is formed, and the cooling water in the heat absorption pipe section 5 is driven to overcome the action of gravity and move upwards. The confluence pipe section 6 is arranged in a horizontal manner above the reactor pressure vessel 7, and its horizontal section is connected to several heat absorption pipe sections 5 so that the cooling liquid after heat absorption is converged. One end of the confluence pipe section 6 is connected to a return pipe section 8, and the return pipe section 8 is connected to the cooling water tank 1. After flowing through the heat absorbing pipe sections 5 connected in parallel, the cooling water is converged in the converging pipe section 6 and finally returns to the cooling water tank 1 to complete the whole natural circulation flow.
Further, the cooling water in the cooling water tank 1 is directly discharged to the external atmosphere in the form of water vapor through the phase change by evaporation. The amount of water stored in the cooling water tank 1 is sufficient to maintain cooling for a period of one week. The staff can supplement water into the cooling water tank 1 through a water pump and other devices.
In addition, in the present embodiment, the pipe diameter of the access pipe section 2 is smaller than the pipe diameter of the heat absorbing pipe section 5. In particular, when the pipe diameter is large, the flow rate of the fluid in the pipe may be slowed down. Therefore, the pipe diameter of the inlet pipe section 2 is selected to be smaller, so that the flow rate of cooling water in the inlet pipe section 2 can be increased. By increasing the pipe diameter of the heat absorption pipe section 5, the flow velocity of the cooling water in the heat absorption pipe section 5 can be slightly slowed down, so that the cooling water can more fully absorb the heat emitted by the pressure vessel 7. Specifically, the pipe diameter of the access pipe section 2 is 180-230mm, and the pipe diameter of the heat absorption pipe section 5 is 250-280mm. Preferably, the pipe diameter of the access pipe section 2 is 200mm. The pipe diameter of the heat absorption pipe section 5 is 250mm.
In this embodiment, each pipe section of the circulation loop is made of stainless steel material. The stainless steel material has good thermal conductivity and strength, and is not easy to deform under heating.
Referring to fig. 3, the practical application and working principle of the present invention are as follows: when the high-temperature gas cooled reactor has an accident, the reactor performs shutdown operation according to the shutdown control signal. After successful shutdown, the decay heat of the fission products generated by the fuel will continue to heat the core, where heat in the reactor needs to be extracted. If the shutdown fails, the fission power of the fuel remains at a higher level, and further heat removal is required.
When a shutdown signal or an operator opening command is received, the control valve 3 of the passive core heat removal system of the present invention is opened to enable the heat removal device to be put into operation. After the control valve 3 is opened, the cooling water stored in the cooling water tank 1 enters the diversion pipe section 4 through the access pipe section 2 under the action of gravity and is diverted in a plurality of heat absorption pipe sections 5 connected in parallel. After the wall surface of the pressure vessel 7 of the reactor is heated due to the fission or decay heat of the reactor core, the temperature is increased, and the heat can heat the cooling water in the heat absorption pipe section 5 through the convection and radiation effects of surrounding air, so that density difference is formed between the cooling water and the fluid in the access pipe section 2, a driving pressure head is generated under the action of gravity, and natural circulation flow is established. After the cooling water has collected in the collecting pipe section 6, it is finally returned to the cooling water tank 1 again. After the cooling water in the cooling water tank 1 is heated up, the heat of the core is introduced into the atmosphere outside the final heat sink through the mechanism of evaporation and boiling.
It can be seen that the passive reactor core heat leading-out device is particularly suitable for horizontally arranged high-temperature gas cooled reactors, can be used for leading out the heat of the reactor core after an accident, relieves the accident consequences and ensures the structural integrity of the reactor.
In summary, the passive core heat removal device has the following beneficial effects:
(1) By adopting a plurality of heat absorption pipe sections 5 which are connected in parallel, and the arrangement positions of the heat absorption pipe sections 5 are closer to the reactor pressure vessel 7, the heat exchange area and coverage range between the heat absorption pipe sections and the wall surface of the reactor pressure vessel 7 are increased, and the heat absorption efficiency from the wall surface of the reactor pressure vessel 7 can be improved, so that the cooling zone heat effect on the reactor core after an accident is improved;
(2) The heat absorption pipe sections 5 are compactly and symmetrically arranged around the reactor pressure vessel 7, so that the uniformity and symmetry of cooling and heat exchange can be improved, the asymmetry of the prior art scheme on cooling of the reactor core is overcome, and the cooling effect of the far-end weak side is improved;
(3) The cooling of the molten scrap bed under accident conditions by passive means is independent of the safety level power supply and the active pump, simplifies the system and equipment, improves the inherent safety of the nuclear power plant and ensures the economical efficiency.
Example 2
The invention also discloses a horizontal high-temperature gas cooled reactor, which comprises a horizontally arranged reactor and the passive reactor core heat leading-out device in the embodiment 1.
Wherein the reactor comprises a core and a pressure vessel 7, the core being housed within the pressure vessel 7. The passive core heat removal device is used to cool down the pressure vessel 7.
The horizontal high temperature gas cooled reactor further includes a control unit electrically connected to the control valve 3 of the passive core heat extraction device in embodiment 1. The control unit is used for sending an opening signal to the control valve 3 when the reactor fails, so that the control valve 3 is opened, and the heat absorption pipe section 5 of the passive reactor core heat leading-out device is used for cooling the pressure vessel 7.
The horizontal high-temperature gas cooled reactor realizes heat export under a fault state through the passive reactor core heat export device, can effectively relieve accident consequences, ensures the structural integrity of the reactor, and further greatly increases the safety performance of the high-temperature gas cooled reactor.
Example 3
The invention also discloses a cooling method of the pressure vessel 7 of the horizontal high-temperature gas cooled reactor, which uses the passive reactor core heat leading-out device in the embodiment 1 and comprises the following steps:
when the reactor fails, the control valve 3 is opened to allow the cooling water in the cooling water tank 1 to flow from the inlet pipe section 2 into the circulation circuit. The cooling water enters the heat absorption pipe section 5 from the access pipe section 2, and the cooling water flowing through the heat absorption pipe section 5 absorbs the heat emitted by the pressure vessel 7. The cooling water after absorbing heat is returned to the cooling water tank 1 through the return pipe section 8.
Specifically, cooling water is supplied from the cooling water tank 1 into the circulation circuit. The temperature of the cooling water should be kept at about 30-35 ℃. The cooling water flows into the circulation loop through the inlet pipe section 2, sequentially flows through the inlet pipe section 2, the heat absorbing pipe section 5 and the return pipe section 8, and finally flows back into the cooling water tank 1 through the return pipe section 8. The cooling water flowing through the heat absorption pipe section 5 can absorb the heat emitted from the pressure vessel 7, so that the pressure vessel 7 is cooled down. The static pressure of the cooling water at the bottommost part of the circulation loop should be kept at 0.12-0.20MPa, and the minimum natural circulation flow rate of the cooling water should be greater than 15kg/s. In the passive core heat extraction device, the cooling water is mainly driven to flow by the gravity head, so that the height difference between the cooling water tank 1 and the pressure vessel 7 needs to be 1000-3000mm to ensure sufficient water pressure for the cooling water.
In summary, the method can safely and rapidly absorb heat and cool the pressure vessel 7.
It is to be understood that the above embodiments are merely illustrative of the application of the principles of the present invention, but not in limitation thereof. Various modifications and improvements may be made by those skilled in the art without departing from the spirit and substance of the invention, and are also considered to be within the scope of the invention.

Claims (11)

1. An passive core heat removal apparatus comprising: a cooling water tank (1), a circulation loop,
the cooling water tank (1) is used for containing cooling water, the position of the cooling water tank (1) is higher than the position of the circulation loop,
the circulating loop comprises an access pipe section (2) and a return pipe section (8), the access pipe section (2) and the return pipe section (8) are both connected with the cooling water tank (1),
the circulation loop also comprises a plurality of heat absorption pipe sections (5), two ends of the heat absorption pipe sections (5) are respectively connected with the access pipe section (2) and the backflow pipe section (8), the plurality of heat absorption pipe sections (5) are sequentially arranged along the horizontal direction and extend along the vertical direction, the heat absorption pipe sections comprise arc-shaped sections, the arc-shaped sections encircle the periphery of a pressure vessel (7) horizontally arranged in the reactor,
the cooling water in the cooling water tank flows into the circulation loop from the connecting pipe section (2), absorbs the heat emitted by the pressure container (7) through the heat absorbing pipe section, and finally flows back into the cooling water tank (1) from the reflux pipe section (8).
2. The device according to claim 1, characterized in that the number of circulation circuits is two, and that the heat absorbing pipe sections (5) of two circulation circuits are symmetrically arranged and located on the left and right sides of the pressure vessel (7), respectively.
3. The device according to claim 1, characterized in that the circulation circuit further comprises a shunt tube section (4);
the diversion pipe section (4) is connected with the access pipe section (2) and is used for diverting the cooling water in the access pipe section (2),
the diversion pipe section (4) extends along the horizontal direction and is also communicated with the lower ends of the plurality of heat absorption pipe sections (5) and used for enabling the diverted cooling water to flow into the heat absorption pipe sections (5).
4. The device according to claim 3, characterized in that the circulation circuit further comprises a confluence pipe section (6), the confluence pipe section (6) being located above the dividing pipe section (4),
the converging pipe section (6) extends along the horizontal direction and is communicated with the upper ends of the plurality of heat absorbing pipe sections (5), the cooling water in the plurality of heat absorbing pipe sections (5) is converged into the converging pipe section (6),
the converging pipe section (6) is also communicated with the backflow pipe section (8) and is used for enabling the converged cooling water to flow back into the cooling water tank (1).
5. The device according to claim 1, characterized in that the access pipe section (2) of the circulation circuit extends in a vertical direction, wherein a control valve (3) is arranged, which control valve (3) is used for controlling the opening or closing of the access pipe section (2).
6. The apparatus of claim 4, wherein each tube segment of the circulation loop is made of stainless steel material.
7. The arrangement according to any of claims 1-6, characterized in that the pipe diameter of the access pipe section (2) is smaller than the pipe diameter of the heat absorbing pipe section (5).
8. The device according to claim 1, characterized in that the distance between the curved section of the heat absorbing pipe section and the pressure vessel (7) is 0.2-0.5 times the diameter length of the pressure vessel.
9. A horizontal high temperature gas cooled reactor comprising a horizontal reactor and the passive core heat removal apparatus of any one of claims 1-8;
the reactor comprises a core and a pressure vessel (7), the core being housed within the pressure vessel (7),
the passive reactor core heat leading-out device is used for cooling the pressure vessel.
10. The horizontal high temperature gas cooled reactor according to claim 9, wherein the passive core heat deriving means employs the passive core heat deriving means as set forth in claim 5,
the system also comprises a control unit which is electrically connected with a control valve (3) of the passive core heat-conducting device,
the control unit is used for sending an opening signal to the control valve (3) when the reactor fails, so that the control valve (3) is opened, and the heat absorption pipe section (5) of the passive reactor core heat conduction device is used for cooling the pressure vessel.
11. A method for cooling a pressure vessel of a horizontal high temperature gas cooled reactor, the method using the passive core heat removal device of any one of claims 1-8, comprising the steps of:
when the reactor fails, the control valve is opened to enable the cooling water in the cooling water tank to flow into the circulation loop through the access pipe section (2),
the cooling water enters the heat absorption pipe section from the access pipe section, the cooling water flowing through the heat absorption pipe section absorbs the heat emitted by the pressure container (7),
the cooling water after absorbing heat is returned to the cooling water tank by the return pipe section.
CN202310281217.3A 2023-03-20 2023-03-20 Passive reactor core heat leading-out device, horizontal high-temperature gas cooled reactor and cooling method Pending CN116525153A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202310281217.3A CN116525153A (en) 2023-03-20 2023-03-20 Passive reactor core heat leading-out device, horizontal high-temperature gas cooled reactor and cooling method

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202310281217.3A CN116525153A (en) 2023-03-20 2023-03-20 Passive reactor core heat leading-out device, horizontal high-temperature gas cooled reactor and cooling method

Publications (1)

Publication Number Publication Date
CN116525153A true CN116525153A (en) 2023-08-01

Family

ID=87400148

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202310281217.3A Pending CN116525153A (en) 2023-03-20 2023-03-20 Passive reactor core heat leading-out device, horizontal high-temperature gas cooled reactor and cooling method

Country Status (1)

Country Link
CN (1) CN116525153A (en)

Similar Documents

Publication Publication Date Title
KR102111813B1 (en) Small modular reactor safety systems
EP2707881B1 (en) Nuclear reactor control method and apparatus
JP2659632B2 (en) Passive cooling safety system for liquid metal cooled reactor
US10636529B2 (en) Reactor vessel reflector with integrated flow-through
JP6236437B2 (en) Core supply water tank and heat removal system for pressurized water type modular small reactor
KR20090021722A (en) Air/water hybrid passive reactor cavity cooling apparatus and method for core decay heat removal of a high temperature gas-cooled reactor
EP2561513B1 (en) Pressure-tube reactor with coolant plenum
CN106229015B (en) A kind of high-temperature molten salt pressure pipe and pipe tube type graphite high-temperature molten salt reactor
JP2014512013A (en) Integrated compact pressurized water reactor
EP0397509B1 (en) Indirect passive cooling system for liquid metal cooled nuclear reactors
US20240029904A1 (en) Integrated passive reactor
CN107170493A (en) A kind of passive containment thermal conduction system
CN102568624A (en) High-temperature supercritical nuclear reactor
US4299660A (en) Heat-extraction system for gas-cooled nuclear reactor
CN116525153A (en) Passive reactor core heat leading-out device, horizontal high-temperature gas cooled reactor and cooling method
US4554129A (en) Gas-cooled nuclear reactor
US4563327A (en) Liquid uranium alloy-helium fission reactor
CN113593733A (en) Passive steel containment heat exporting system
JP2003139881A (en) Reactor cooled with supercritical pressure water, channel box, water rod and fuel assembly
CN113241200A (en) Fuel salt loop system and operation method
CN111933315A (en) Passive residual heat removal system and method for pool type lead-based reactor
CN112420226B (en) Passive residual heat removal system based on annular air cooler
CN109585045B (en) Heat exchange device for reactor and passive residual heat removal system
FI129308B (en) A nuclear reactor module and a nuclear district heating reactor comprising and method of operating the same
CN209249091U (en) A kind of heat-exchanger rig and residual heat removal system for reactor waste discharge

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination