CN111899901A - Passive and active combined molten material in-pile retention cooling system - Google Patents
Passive and active combined molten material in-pile retention cooling system Download PDFInfo
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- CN111899901A CN111899901A CN202010808337.0A CN202010808337A CN111899901A CN 111899901 A CN111899901 A CN 111899901A CN 202010808337 A CN202010808337 A CN 202010808337A CN 111899901 A CN111899901 A CN 111899901A
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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
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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
- G21C15/24—Promoting flow of the coolant
- G21C15/26—Promoting flow of the coolant by convection, e.g. using chimneys, using divergent channels
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention relates to the technical field of nuclear cooling systems, in particular to a passive and active combined molten material in-pile retention cooling system, which adopts the following technical scheme: the passive cooling system comprises a pressure vessel external cooling structure, a passive cooling subsystem and an active cooling subsystem, wherein the pressure vessel external cooling structure comprises a primary side shielding water tank; the passive cooling subsystem comprises a first cooler, and the first cooler is connected with the flow channel of the heat-insulating layer; the active cooling subsystem comprises a second cooler, a secondary loop reserve tank and a water injection pump, wherein the second cooler, the secondary loop reserve tank and the water injection pump are sequentially connected between the outlet and the inlet of the heat-insulating layer runner in series. The device can quickly submerge the flow channel of the heat-insulating layer and cool the outside of the pressure vessel, reduces the requirements of the primary side shielding water tank or the secondary circuit standby water tank on the water filling amount and the water level height, and is very suitable for floating nuclear power plants and other nuclear reactors with limited space and water sources.
Description
Technical Field
The invention relates to the technical field of nuclear cooling systems, in particular to a passive and active combined molten material in-pile retention cooling system.
Background
After the fukushima nuclear accident, the concern of the international society on the serious accident of the nuclear power plant is remarkably enhanced. After the accident, the reactor core is exposed, heated and melted due to loss of cooling, and the molten substances in the reactor core are relocated to the lower end cover of the pressure vessel and can continuously melt through the lower end cover of the pressure vessel, so that a large amount of radioactive substances are released.
Therefore, in the third generation nuclear power technology, the cooling and retention measures of the core melt become the key strategy for eliminating the release of a large amount of radioactivity internationally. Although melt pressure vessel cooling and retention strategies are currently employed, there are variations in the specific embodiments. At present, the design scheme of a passive reactor cavity water injection cooling system based on natural circulation is adopted internationally, and the design scheme of an active reactor cavity water injection system is adopted for a small part. After a serious accident, gravity water is injected into the reactor cavity through the cooling water tank to submerge the reactor cavity, the bottom inlet floating plug of the flow channel of the heat-insulating layer of the pressure container is opened under the action of buoyancy, and the lower seal head and the outer wall surface of the cylinder are cooled through the flow channel of the heat-insulating layer of the pressure container. The steam-water mixture pushes away a top cover plate of a flow channel of a heat-insulating layer of the pressure container and flows back to a water return channel outside the reactor cavity, and the water return channel outside the reactor cavity is communicated with the lower part of the reactor cavity to form circulation. Water in the flow channel of the heat-insulating layer forms natural circulation flow with the descending section of the water return channel outside the reactor cavity as the ascending section, so that long-term cooling of the pressure container is realized.
At present, in-service marine nuclear reactors do not consider the measures for coping with and relieving serious accidents, and newly designed nuclear reactors such as floating nuclear power stations and the like are required to have the measures for coping with and relieving the serious accidents. Therefore, based on the operating environment of nuclear reactors such as floating nuclear power plants and the restriction of space water sources, research and development are needed to design a passive and active molten material in-reactor retention cooling system to realize the cooling and retention of the molten material in the nuclear reactor pressure vessel.
Disclosure of Invention
Aiming at the technical problem that the cooling and detention of the reactor core melt in the nuclear reactor pressure vessel need to be realized, the invention provides a melt in-reactor detention cooling system combining passive and active, which can effectively cool the reactor pressure vessel under the serious accident so as to realize the cooling and detention of the reactor core melt in the nuclear reactor pressure vessel.
The invention is realized by the following technical scheme:
a passive and active combined molten mass in-pile retention cooling system comprises a pressure container external cooling structure, wherein the pressure container external cooling structure comprises a primary side shielding water tank, and the water outlet end of the primary side shielding water tank is connected with a first stop valve and a first check valve in sequence and then is connected with the water inlet end of a flow passage of a heat insulation layer; the passive cooling subsystem and the active cooling subsystem are also included; the passive cooling subsystem comprises a first cooler, the water inlet end of a heat pipe of the first cooler is connected with the water outlet end of the flow channel of the heat-insulating layer, and a second stop valve is connected between the first cooler and the flow channel of the heat-insulating layer; the water outlet end of the first cooler heat pipe is connected with the third stop valve and then is connected with the water inlet end of the heat-insulating layer flow passage; the energy-kinetic energy cooling subsystem comprises a second cooler, the water inlet end of a heat pipe of the second cooler is connected with the water outlet end of a second check valve, and a fourth stop valve is connected between the second cooler and the second check valve; and the water outlet end of the second cooler heat pipe is connected with the water inlet end of the heat-insulating layer flow channel after being sequentially connected with the second loop standby water tank, the water injection pump and the fifth stop valve.
When the reactor is used, under the normal operation condition of the reactor, the pressure container, the heat-insulating layer flow channel and the inlet and outlet pipelines are in an air state, the valve of the external cooling structure of the pressure container, the first stop valve and the second stop valve are closed, and the seawater inlet and the seawater outlet of the first cooler are connected with seawater; because the gap of the flow passage of the heat insulation layer is small, the requirement on the volume of water for cooling the outside of the pressure vessel is small, and the device is very suitable for nuclear reactors such as floating nuclear power stations with limited space and water sources.
When a reactor has a serious accident, the passive water injection working condition is as follows: the method comprises the steps that firstly, a valve of an external cooling structure of the pressure container is opened to inject water to a flow passage of a heat insulation layer by gravity, a floating plug at the bottom inlet of the flow passage of the heat insulation layer of the pressure container is opened under the action of buoyancy, a lower seal head and the outer wall surface of a cylinder body of the pressure container are cooled by the flow passage of the heat insulation layer of the pressure container, part of water is vaporized, water vapor and air are discharged to a reactor cavity through an outlet of the flow passage of the heat insulation layer to submerge a reactor cavity, and part of water is vaporized, and. And simultaneously opening a second stop valve of the first cooler outlet pipeline and a third stop valve on the outlet pipeline, so that the first cooler loop is communicated with the heat-insulating layer flow passage to form a closed circulating flow loop.
The steam-water mixture flows from top to bottom through the inner side of the heat transfer pipe of the first cooler and is cooled into supercooled water by seawater outside the heat transfer pipe of the first cooler; the seawater outside the heat transfer pipe of the first cooler is heated and flows passively from bottom to top, the colder seawater enters the bottom seawater side of the first cooler through the bottom inlet pipeline, the heated seawater enters the seawater through the upper outlet pipeline, and the supercooled seawater is a final heat sink which takes out the heat of the reactor core. And then the steam-water mixture in the flow passage of the heat insulation layer is used as an ascending section, cold water on the inner side of the lower heat transfer pipe of the first cooler is used as a descending section, closed natural circulation flow is formed by depending on the density difference and the potential difference of cold and hot fluids, and the cooling and the detention of the reactor core melt in the pressure vessel are realized through long-term passive cooling outside the pressure vessel.
When a reactor has a serious accident, the active water injection working condition of the system is as follows: firstly, opening a water injection pipeline stop valve and a fifth stop valve of a secondary loop standby water tank, and starting a water injection pump; water in the two-loop reserve water tank is injected into the flow channel of the heat insulation layer, part of water is vaporized due to the high-temperature state of the wall surface of the pressure container, a steam-water mixture and air enter the second cooler through the outlet main channel to be cooled by seawater, and cooling water flows back to the two-loop reserve water tank. Namely, the second cooler loop is communicated with the heat-insulating layer flow channel through the two-loop standby water tank and the water injection pump to form a closed active circulating flow loop. And then the molten reactor core is cooled and retained in the pressure vessel through long-term active cooling outside the pressure vessel, and the seawater is a final heat sink for taking out the heat of the reactor core.
Wherein the active water injection working condition is that the fluid form at the outlet of the runner of the insulating layer is determined according to the decay heat of the reactor core and the active water injection flow. When the core decay heat is small and the active water injection flow rate is large, the fluid at the outlet of the flow passage of the heat insulation layer can be a single-phase flow or a steam-water mixture or even steam. Therefore, the flow rate of active water injection needs to be determined according to the decay heat of the reactor core, and the fluid at the outlet of the flow passage of the heat-insulating layer is ensured to be a single-phase flow or a steam-water mixture.
In conclusion, the active cooling subsystem operates alone, the pressure vessel external cooling structure operates alone in combination with the passive cooling subsystem, water can be directly injected into the pressure vessel heat-insulating layer flow channel, the heat-insulating layer flow channel and the pressure vessel exterior can be quickly submerged, the requirements of the primary side shielding water tank or the secondary circuit standby water tank on the water filling amount and the water level height are reduced, and the floating nuclear power station is very suitable for floating nuclear power stations and other nuclear reactors with limited space and water sources. And the advantages of the passive and active cooling systems are combined, the requirement on the arrangement height of the first cooler is reduced, and the arrangement of system equipment is facilitated.
Preferably, a third check valve is connected between the third stop valve and the water inlet end of the heat insulation layer flow passage to prevent the fluid in the heat insulation layer flow passage from flowing back to the first cooler.
Furthermore, a fluctuation water tank is connected between the first cooler and the second stop valve, and a fourth check valve is connected to a water outlet end of the fluctuation water tank. In the later stage of operation of the cooler system, the heat brought out by the system is reduced along with the heat attenuation of the melt, the flow channel of the heat-insulating layer is gradually changed into single-phase water from a steam-water mixture, and the volume of the system is shrunk; thus by providing a surge tank, the volume of water that contracts the system can be replenished.
Preferably, the bottom ends of the heat transfer tubes of the first cooler are higher than the center line of the core active area, so that the natural circulation capacity is further improved by increasing the difference of the cold and hot fluid levels.
Furthermore, a second check valve is connected between the second stop valve and the water outlet end of the heat-insulating layer flow passage to prevent the fluid from flowing back to the heat-insulating layer flow passage.
Preferably, a safety valve is further connected between the second check valve and the water outlet end of the flow passage of the heat insulation layer, so that the pressure of the whole cooling system is prevented from being too high, and the operation safety of the system is ensured.
Preferably, 2n outlet pipelines are annularly and uniformly distributed at the top of the heat-insulating layer flow channel, n is a natural number greater than zero, and every two outlet pipelines are converged to finally form an outlet main pipe.
Preferably, the safety valve is arranged on the outlet main pipe and is positioned on the inner side of the reactor cabin wall.
Preferably, the inner side wall of the insulating layer structure is lined with a stainless steel baffle plate so as to prevent fluid in the flow channel of the insulating layer from leaking from the insulating layer structure.
Specifically, the heat-insulating layer structure wraps the lower seal head and the straight cylinder body of the pressure vessel.
The invention has the following advantages and beneficial effects:
1. the primary side shielding water tank and/or the secondary circuit reserve water tank are/is adopted to directly inject water into the flow channel of the pressure vessel heat-insulating layer, and the volume of the flow channel of the heat-insulating layer is very small, so that the flow channel of the heat-insulating layer can be quickly submerged and the outside of the pressure vessel can be cooled, the requirements of the primary side shielding water tank or the secondary circuit reserve water tank on the water filling amount and the water level height are reduced, and the primary side shielding water tank and/or the secondary circuit reserve.
2. A closed circulation flow loop is formed by the second cooler and the heat-insulating layer flow passage, active circulation flow is formed by the driving of a water supply pump, seawater is used as a final heat sink, and then the cooling and detention of the reactor core melt in the pressure vessel are realized by long-term active cooling outside the pressure vessel
3. A closed circulating flow loop is formed by the first cooler and the heat-insulating layer flow channel, closed natural circulating flow is formed by the density difference and the potential difference of cold and hot fluids, seawater is used as a final heat sink, and then the cooling and detention of the reactor core melt in the pressure vessel are realized by long-term passive cooling outside the pressure vessel.
4. The advantages of the passive and active cooling systems are combined, the requirement on the arrangement height of the second cooler is lowered, and system equipment arrangement is facilitated.
Drawings
The accompanying drawings, which are included to provide a further understanding of the embodiments of the invention and are incorporated in and constitute a part of this application, illustrate embodiment(s) of the invention and together with the description serve to explain the principles of the invention. In the drawings:
FIG. 1 is a schematic view of the piping connection of the present invention;
fig. 2 is a schematic diagram of the arrangement of components of the present invention.
Names of various parts in the drawings:
10-hull, 20-stack wall, 100-primary side shield water tank, 101-first stop valve, 102-first check valve, 103-inlet pipe, 104-insulation structure, 105-insulation flow channel, 106-pressure vessel, 107-outlet pipe, 108-outlet main, 109-safety valve, 110-second check valve, 111-second stop valve, 113-first outlet valve, 114-first inlet valve, 115-first cooler, 116-third stop valve, 117-third check valve, 121-fourth stop valve, 123-second outlet valve, 124-second inlet valve, 125-second cooler, 130-second return water tank, 131-fifth check valve, 132-fifth stop valve, 135-water injection pump, 140-surge tank, 141-fourth check valve.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention is further described in detail below with reference to examples and accompanying drawings, and the exemplary embodiments and descriptions thereof are only used for explaining the present invention and are not meant to limit the present invention.
Examples
A passive and active combined molten mass in-pile retention cooling system comprises a pressure vessel external cooling structure, a passive cooling subsystem and an active cooling subsystem.
Specifically, the pressure vessel external cooling structure includes: a primary side shield water tank 100 disposed in the reactor compartment around an insulation layer structure 104 of a pressure vessel 106; the heat-insulating layer structure 104 wraps the lower end enclosure and the straight cylinder body of the pressure vessel 106, a heat-insulating layer flow channel 105 is formed between the heat-insulating layer structure 104 and the outer wall surface of the pressure vessel 106, and the gap of the heat-insulating layer flow channel 105 is between 60mm and 180mm, so that the volumes of the heat-insulating layer flow channel 105 and an inlet pipeline are 4m3To 6m3Left and right; the bottom of the insulating layer flow channel 105 is provided with an insulating layer flow channel inlet pipeline 103. Wherein, the water outlet pipeline at the lower part of the primary side shielding water tank 100 is provided with a normally closed electric valve and a check valve and is connected with a water injection inlet pipeline 103 at the bottom of the structure of the insulating layer runner 105. Namely, the external cooling structure of the pressure vessel comprises a primary side shielded water tank 100, and the water outlet end of the primary side shielded water tank 100 is connected with the water inlet end of an insulating layer flow passage 105 through an inlet pipeline 103 after being sequentially connected with a first stop valve 101 and a first check valve 102.
While the inside walls of the insulation layer structure 104 are lined with stainless steel baffles to prevent fluid in the insulation layer flow channels 105 from leaking out of the insulation layer structure 104. The stainless steel lining plate and the outer wall surface of the pressure vessel 106 together form an insulating layer flow passage 105. 2n outlet pipelines 107 are annularly and uniformly distributed at the top of the heat-insulating layer flow passage 105, n is a natural number greater than zero, and every two outlet pipelines 107 are converged to finally form an outlet header pipe 108; in the embodiment, 8 to 12 outlet pipes (with the pipe inner diameter of between 80 and 120 mm) are uniformly and circumferentially arranged on the top of the insulating layer flow channel 105 surrounding the lower cylinder of the pressure vessel 106 and penetrate through the insulating layer structure 104 to be connected with the insulating layer flow channel 105. That is, the outlet pipes 107 are combined two by two, and finally combined into an outlet main 108, so as to reasonably arrange the pipes in a narrow space at the upper end of the pressure vessel 106.
The passive cooling subsystem includes a first cooler 115; the water inlet end of the first cooler 115 is connected with the water outlet end of the insulating layer runner 105, and a second stop valve 111 is connected between the first cooler 115 and the insulating layer runner 105; the water outlet end of the first cooler 115 is connected with the water inlet end of the insulating layer runner 105 after being connected with the third stop valve 116. It can be appreciated that the first cooler 115 is provided with a first outlet valve 113, a first inlet valve 114 to be connected to the seawater inlet port through the first inlet valve 114, and to the seawater return port through the first outlet valve 113, even though the cold pipes of the first cooler 115 are connected to the seawater.
Furthermore, an electric safety valve 109 is arranged at a section of the outlet main pipe 108 of the insulation layer flow passage 105, which is located at the inner side of the reactor wall 20, and a second check valve 110 is arranged at a section of the outlet main pipe 108 of the insulation layer flow passage 105, which is located at the outer side of the reactor wall 20, i.e. the safety valve 109 is further connected between the second check valve 110 and the water outlet end of the insulation layer flow passage 105, so as to prevent the pressure of the whole cooling system from being too high, and ensure the. The relief valve 109 functions as: (1) under the passive water injection working condition, air is discharged to the reactor cabin by opening a safety valve, so that the primary side shielding water tank 100 and the heat-insulating layer runner 105 form a U-shaped pipe, and gravity water injection from the primary side shielding water tank 100 to the heat-insulating layer runner 105 is accelerated; (2) the passive operation working condition maintains the pressure of the passive cooling system, and the safe operation of the system is ensured. The second check valve 110 functions to: the fluid is prevented from flowing back to the insulating layer flow passage 105 to cool down thermal shock caused by the outside of the pressure vessel 106 during normal operation of the reactor.
Further, a third check valve 117 is connected between the third stop valve 116 and the water inlet end of the insulation layer flow passage 105 to prevent the fluid in the insulation layer flow passage 105 from flowing back to the first cooler 115.
Furthermore, a surge tank 140 is connected between the first cooler 115 and the second stop valve 111, and a fourth check valve 141 is connected to an outlet of the surge tank 140. In the later stage of operation of the cooler system, the heat brought out by the system is reduced along with the heat attenuation of the melt, the flow channel 105 of the heat-insulating layer is gradually changed into single-phase water from a steam-water mixture, and the volume of the system is shrunk; thus, by providing a surge tank 140, the volume of water that contracts the system can be replenished.
Preferably, the bottom ends of the heat transfer tubes of the first cooler 115 are higher than the centerline of the core active area to further improve natural circulation capacity by increasing the difference in the cold and hot fluid levels.
For an active cooling subsystem, the active cooling subsystem includes a second cooler 125; the water inlet end of the heat pipe of the second cooler 125 is connected with the water outlet end of the insulating layer flow channel 105, and a fourth stop valve 121 is connected between the second cooler 125 and the insulating layer flow channel 105. The water outlet end of the heat pipe of the second cooler 125 is connected with the water inlet end of the insulating layer flow channel 105 after being sequentially connected with the second loop standby water tank 130, the water injection pump 135 and the fifth stop valve 132.
A second check valve 110 is connected between the second stop valve 111 and the water outlet end of the insulating layer flow passage 105 to prevent the fluid from flowing back into the insulating layer flow passage 105. That is, the water inlet of the heat pipe of the second cooler 125 is connected to the water outlet of the second check valve 110, and the fourth stop valve 121 is connected between the second cooler 125 and the second check valve 110.
Likewise, the second cooler 125 is provided with a second outlet valve 123, a second inlet valve 124 to be connected to the seawater inlet end through the second inlet valve 124 and to the seawater return end through the second outlet valve 123, even though the cold pipe of the second cooler 125 is connected to the outside seawater.
It should be noted that the stop valve and the safety valve in this embodiment are both electrically operated valves, so as to facilitate the operation of the remote operation system; and the stop valve and the safety valve related in the embodiment are both connected with a reliable power supply and a storage battery, so that the on-off of the whole ship after power failure can be ensured. For a floating nuclear reactor, the second cooler 125 and the first cooler 115 are arranged substantially symmetrically port and starboard with a cooling capacity of 2 x 100%.
The working principle of the embodiment is as follows:
the active operation mode comprises the following steps:
when the core outlet temperature reaches 650 c during a serious accident, if the water injection pump 135 is normally started, the operator first opens the fifth cut-off valve 132 connected to the two-circuit reserver tank 130 and the fourth cut-off valve 121 of the heat transfer pipe inlet piping of the second cooler 125 within a certain delay time and starts the water injection pump 135. At this time, the two-circuit backup water tank 130 injects water into the insulating layer flow channel 105, since the wall surface of the pressure vessel 106 is in a high temperature state, part of the water is vaporized, the steam-water mixture and the air enter the second cooler 125 through the outlet header 108 of the insulating layer flow channel 105 to be cooled by the seawater, and the cooled water flows back to the two-circuit backup water tank 130. That is, the second cooler 125 is communicated with the insulating layer flow passage 105 through the second circuit backup water tank 130 and the water injection pump 135, thereby forming a closed active circulation flow circuit. The cooling and retention of the core melt within the pressure vessel 106 is then achieved by long term active cooling outside the pressure vessel 106, while the seawater is the ultimate heat sink that carries away the core heat.
Wherein, the single-phase water or the steam-water mixture flows from top to bottom through the inner side of the heat transfer pipe of the second cooler 125, and is cooled into the supercooled water by the seawater outside the heat transfer pipe of the second cooler 125; the seawater outside the heat transfer tubes of the second cooler 125 is heated and passively flows from bottom to top, the cooler seawater enters the bottom seawater side of the second cooler 125 through a second inlet valve 124 (normally open hydraulic butterfly valve) on the bottom inlet pipe, and the heated seawater enters the seawater through a second outlet valve 123 on the upper outlet pipe (normally open hydraulic butterfly valve).
The passive operation mode comprises the following steps:
when the temperature of the reactor core outlet reaches 650 ℃ during a serious accident, if the water supply pump 135 loses power supply or fails to start, an operator opens the first stop valve 101 of the water injection pipeline of the primary side shield water tank 100 within a certain delay time and locks and opens the electric safety valve 109 of the outlet main pipe 108 of the insulating layer flow passage 105, water in the primary side shield water tank 100 is injected into the insulating layer flow passage 105 by gravity, and the water enters the insulating layer flow passage 105 and submerges the outside of the cooling pressure vessel 106. The air in the insulating layer flow passage 105 and the water vapor generated by the action with the outer wall surface of the pressure vessel 106 in a high temperature state are discharged into the reactor chamber through the electric safety valve 109 of the outlet header pipe 108 of the insulating layer flow passage 105. After the water vapor passes through the electrical safety valve 109, the electrical safety valve 109 is closed after a certain delay time, and thereafter the electrical safety valve 109 is operated according to the opening/closing setting value.
After the electric safety valve 109 is closed, the third stop valve 116 of the outlet pipe and the second stop valve 111 of the inlet pipe of the first cooler 115 are simultaneously opened, and the first cooler 115 is communicated with the heat insulation layer flow passage 105 to form a closed circulation flow circuit. The cooling and retention of the core melt within the pressure vessel 106 is then achieved by long term passive cooling of the exterior of the pressure vessel 106, while the seawater is the ultimate heat sink that carries away the core heat. The operating pressure of the closed natural circulation flow circuit is protected by the electric safety valve 109 according to the opening/closing pressure setting value.
The steam-water mixture flows from top to bottom through the inner side of the heat transfer pipe of the first cooler 115 and is cooled into supercooled water by the seawater outside the heat transfer pipe of the first cooler 115; the seawater outside the heat transfer tubes of the first cooler 115 is heated and passively flows from bottom to top, the cooler seawater enters the bottom seawater side of the first cooler 115 through a bottom first inlet valve 114 (normally open hydraulic butterfly valve), the heated seawater enters the seawater through an upper outlet pipe first outlet valve 113 (normally open hydraulic butterfly valve), and the subcooled seawater is a final heat sink which takes away the heat of the reactor core.
In the later stage of the operation of the system, the heat brought out by the system is reduced along with the heat attenuation of the melt, the flow channel 105 of the heat-insulating layer is gradually changed into one-way water from the steam-water mixture, the volume of the system is contracted, and the contracted water volume is provided by the fluctuation water tank 140 at the inlet of the first cooler 115.
Therefore, the present embodiment can combine the advantages of the passive and active cooling systems, and reduce the requirement for the arrangement height of the second cooler 125, which is beneficial to the arrangement of the system equipment. Because the clearance of the heat-insulating layer flow passage is small, the volumes of the pressure vessel heat-insulating layer flow passage and the inlet pipeline are 4m3To 6m3Left and right, outlet pipe volume about 0.5m3. Thus, a pressure vessel was madeThe volume of water cooled outside the vessel 106 is required to be small, and the vessel is very suitable for nuclear reactors such as floating nuclear power stations with limited space and water sources.
The above-mentioned embodiments are intended to illustrate the objects, technical solutions and advantages of the present invention in further detail, and it should be understood that the above-mentioned embodiments are merely exemplary embodiments of the present invention, and are not intended to limit the scope of the present invention, and any modifications, equivalent substitutions, improvements and the like made within the spirit and principle of the present invention should be included in the scope of the present invention.
Claims (10)
1. A passive and active combined molten mass in-pile retention cooling system comprises a pressure vessel external cooling structure, wherein the pressure vessel external cooling structure comprises a primary side shielding water tank (100), and the water outlet end of the primary side shielding water tank (100) is connected with a first stop valve (101) and a first check valve (102) in sequence and then is connected with the water inlet end of a heat insulation layer flow passage (105), and the passive and active combined molten mass in-pile retention cooling system is characterized by further comprising a passive cooling subsystem and an active cooling subsystem;
the passive cooling subsystem comprises a first cooler (115), the water inlet end of a heat pipe of the first cooler (115) is connected with the water outlet end of the heat-insulating layer flow channel (105), a second stop valve (111) is connected between the first cooler (115) and the heat-insulating layer flow channel (105), and the water outlet end of the heat pipe of the first cooler (115) is connected with the water inlet end of the heat-insulating layer flow channel (105) after being connected with a third stop valve (116);
the active cooling subsystem comprises a second cooler (125), the water inlet end of the heat pipe of the second cooler (125) is connected with the water outlet end of a second check valve (110), a fourth stop valve (121) is connected between the second cooler (125) and the second check valve (110), and the water outlet end of the heat pipe of the second cooler (125) is connected with the water inlet end of a heat insulation layer flow channel (105) after being sequentially connected with a second loop standby water tank (130), a water injection pump (135) and a fifth stop valve (132).
2. A combined passive and active molten mass in-pile stagnant cooling system according to claim 1, characterized in that a third check valve (117) is connected between the third shut-off valve (116) and the water inlet end of the insulating layer flow channel (105).
3. A combined passive and active molten mass in-pile stagnant cooling system according to claim 1, characterized in that a surge tank (140) is connected between the first cooler (115) and the second shut-off valve (111), and a fourth check valve (141) is connected to the outlet end of the surge tank (140).
4. The combined passive and active molten iron in-core stagnant cooling system of claim 1, characterized in that the bottom ends of the heat transfer tubes of the first cooler (125) are higher than the core active zone centerline.
5. The passive and active combined molten mass in-pile stagnant cooling system of claim 1, characterized in that a second check valve (110) is connected between the second stop valve (111) and the water outlet end of the insulating layer flow passage (105).
6. The passive and active combined molten mass in-pile stagnant cooling system of claim 5, characterized in that a safety valve (109) is further connected between the second check valve (110) and the water outlet end of the insulating layer flow passage (105).
7. The passive and active combined molten mass in-pile retention cooling system according to claim 6, wherein 2n outlet pipelines (107) are annularly and uniformly distributed at the top of the insulating layer flow channel (105), n is a natural number larger than zero, and the outlet pipelines (107) are combined in pairs to finally form an outlet header pipe (108).
8. A combined passive and active molten iron hold-up cooling system according to claim 7, characterized in that the safety valve (109) is arranged on the outlet manifold (108) inside the reactor bulkhead (20).
9. The passive and active combined smelt within the reactor stagnant cooling system according to claim 1, characterized in that said insulation layer flow channel (105) is a cavity between the inner wall of the insulation layer structure (104) and the outer wall of the pressure vessel (106), the inner side wall of said insulation layer structure (104) being lined with stainless steel baffles.
10. The combined passive and active molten mass in-pile stagnant cooling system of claim 1, characterized in that the insulation layer structure (104) wraps up the bottom head and the straight cylinder of the pressure vessel (106).
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| CN202010808337.0A CN111899901A (en) | 2020-08-12 | 2020-08-12 | Passive and active combined molten material in-pile retention cooling system |
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| CN202010808337.0A CN111899901A (en) | 2020-08-12 | 2020-08-12 | Passive and active combined molten material in-pile retention cooling system |
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