CN211858171U - Water replenishing safety system used in nuclear power station containment and refueling water tank thereof - Google Patents

Abstract

The utility model discloses a refueling water tank that is used for moisturizing safety coefficient in nuclear power station containment and moisturizing safety coefficient that has it, refueling water tank includes: the water-absorbing device comprises a shell, a sprayer and a first heat-absorbing device, wherein a water containing cavity is formed in the shell, and a safety injection port communicated with the water containing cavity is formed in the shell; one end of the sprayer extends into the water containing cavity; the first heat absorbing device is internally provided with a phase change material and is arranged in the water containing cavity. According to the utility model discloses a reloading water tank, when the sprinkler to hold the intracavity spout into a large amount of high temperature steam and water and make the ann's notes temperature of holding the intracavity of water and rise, first heat absorbing device can reduce the ann and annotate the temperature through phase change heat absorption of phase change material, guarantee to follow the interior ann's water injection of inputing into reactor pressure vessel in the casing and be in safe temperature range, thereby realize submerging for a long time and cooling of the reactor core in the reactor pressure vessel, make the pressure boundary of fuel rod parcel radioactive substance inefficacy not, prevent the emergence of serious radioactivity condition of leaking.

Description

Water replenishing safety system used in nuclear power station containment and refueling water tank thereof

Technical Field

The utility model belongs to the technical field of nuclear power safety and specifically relates to a moisturizing safety coefficient that is used for nuclear power station containment in refueling water tank of moisturizing safety coefficient and has it in nuclear power station containment is related to.

Background

In the related art, when an accident occurs in a nuclear power plant, particularly a pressurized water reactor nuclear power plant, the accident is relieved and eliminated mainly by a core cooling system, a containment cooling system and the like. The reactor core cooling system realizes long-term submergence and cooling of the reactor core by injecting cooling water with lower temperature into the reactor core, so that the pressure boundary of the radioactive substance wrapped by the fuel rod is not invalid, and the serious radioactive leakage is prevented. The containment cooling system ensures that the temperature and pressure rise in the containment does not exceed the safety limit value during an accident through measures such as cooling, waste heat discharge, pressure reduction and the like of the containment, ensures the integrity of the pressure boundary of the containment, and prevents a large amount of radioactive substances from being released to the environment.

In a reactor core cooling system, such as an AP/CAP series of three-generation passive reactor core cooling system, the water temperature of a safety injection system has great influence on whether the reactor core can be effectively submerged and the cooling, if the safety injection water temperature in a containment built-in refueling water tank has great influence on the safety of the reactor core, the possibility that a pressure stabilizer cannot effectively drain water to enter the reactor core is increased due to the overhigh safety injection water temperature in the containment built-in refueling water tank, the gas production rate of the reactor core is overhigh, the pressure in the reactor core is larger, and the safety injection flow of the containment built-in refueling water tank is influenced or delayed, so that the risk that the liquid level of the reactor core is lower and the reactor core cannot be effectively cooled is increased. Before safety injection of the safety shell built-in refueling water tank is started, the automatic depressurization system sprays a large amount of high-temperature steam and water of the main loop into the safety shell built-in refueling water tank, so that the safety injection water temperature in the safety shell built-in refueling water tank is greatly improved, and the safety injection water temperature is unfavorable for the reactor core safety.

In containment systems, there is a maximum pressure limit in the containment due to the containment design pressure. The pressure in the containment vessel is closely related to the temperature in the containment vessel, so that the pressure in the containment vessel is inevitably increased when the temperature in the containment vessel is increased, and when the heat in the containment vessel is difficult to carry out, the temperature and the overpressure in the containment vessel can be generated, and the integrity of the containment vessel as a pressure boundary is threatened.

The key to both of these is the need to raise the temperature beyond its required or safe limit.

SUMMERY OF THE UTILITY MODEL

The utility model discloses aim at solving one of the technical problem that exists among the prior art at least. Therefore, the utility model provides a refueling water tank that is used for moisturizing safety coefficient in nuclear power station containment, refueling water tank can reduce the safety injection temperature.

The utility model also provides a moisturizing safety coefficient that is used for in the nuclear power station containment that has above-mentioned reloading water tank.

According to the utility model discloses a reloading water tank that is used for moisturizing safety coefficient in nuclear power station containment of first aspect, include: the device comprises a shell, a water storage cavity is arranged in the shell, and a safety injection port communicated with the water storage cavity is arranged on the shell; the sprinkler is provided with one end extending into the water containing cavity; the phase change material is arranged in the first heat absorption device, and the first heat absorption device is arranged in the water containing cavity.

According to the utility model discloses a refueling water tank for moisturizing safety coefficient in nuclear power station containment, through the first heat sink that is equipped with phase change material in holding the water intracavity, make when the sprinkler to holding the water intracavity spout into a large amount of high temperature steam and water and make the interior ann of holding the water intracavity annotate the temperature and rise, first heat sink can reduce ann and annotate the temperature through phase change heat absorption of phase change material, guarantee to follow the interior ann water of inputing in the reactor pressure vessel of casing and be in safe temperature range, thereby realize flooding and cooling for a long time of the reactor core in the reactor pressure vessel, make the pressure boundary of fuel rod parcel radioactive substance inefficacy, prevent the emergence of serious radioactivity leakage condition.

According to some embodiments of the invention, the first heat absorbing means is located between the one end of the sprinkler and the pour spout.

According to some embodiments of the present invention, a heat absorbing passage is formed in the first heat absorbing device, and an outlet of the heat absorbing passage communicates to the ampoule inlet.

Further, the cross-sectional area of any section of the heat absorption channel is larger than that of the injection port.

According to some embodiments of the invention, a horizontally extending bottom plate is provided in the housing, the bottom plate being arranged close to the bottom wall of the housing, the first heat absorbing means being fixed on the bottom plate, and the first heat absorbing means being located below the one end of the sprinkler.

Further, the first heat sink is removably attached to the base plate.

According to some embodiments of the invention, the phase change temperature of the phase change material is in the range of 40 ℃ to 90 ℃.

In some embodiments of the present invention, the heat transfer surface of the first heat absorbing device is provided with a plurality of heat transfer ribs.

According to some embodiments of the present invention, the phase change material is adapted to perform an endothermic reaction with the gas or liquid in the water containing chamber.

According to some embodiments of the invention, the first heat sink is configured to deposit the phase change material into the refueling water tank when the refueling water tank reaches a heat absorption condition.

According to the utility model discloses a moisturizing safety coefficient for in nuclear power station containment of second aspect, include: the reactor pressure vessel is arranged in the containment vessel, the top of the reactor pressure vessel is provided with a pressure relief port, and the lower part of the reactor pressure vessel is provided with a water replenishing port; according to the utility model discloses a refueling water tank that is used for moisturizing safety coefficient in nuclear power station containment of first aspect, refueling water tank locates in the containment, wherein, being located of sprinkler the other end in the casing outside with the pressure release mouth is linked together, ann annotate the mouth with the moisturizing mouth is linked together.

According to the utility model discloses a moisturizing safety coefficient for in nuclear power station containment through setting up the refueling water tank of the moisturizing safety coefficient for in the nuclear power station containment of above-mentioned first aspect, can continuously provide microthermal ann's water injection for in the reactor pressure vessel, delay reactor pressure vessel's intensification and step up to reduce the probability that the radioactivity leaked the occurence of failure.

According to some embodiments of the utility model, the moisturizing safety coefficient still includes: and the second heat absorption device is arranged in the containment and is used for absorbing the heat of the gas or the liquid in the containment.

Further, the second heat sink is a phase change heat sink, and the phase change material is filled in the second heat sink.

Furthermore, the phase change temperature of the phase change material in the second heat sink is lower than the saturation temperature corresponding to the design pressure of the containment vessel.

Additional aspects and advantages of the invention will be set forth in part in the description which follows and, in part, will be obvious from the description, or may be learned by practice of the invention.

Drawings

Fig. 1 is a schematic diagram of a refueling water tank for a nuclear power plant in-containment water replenishment safety system according to a first aspect of the present invention.

Reference numerals:

the refueling water tank 100:

a shell 1, a water containing cavity 11, a safety injection port 12, a bottom plate 13,

the number of the sprinklers 2 is such that,

a first heat sink 3, a heat sink channel 31, a phase change material 32.

Detailed Description

Reference will now be made in detail to embodiments of the present invention, examples of which are illustrated in the accompanying drawings, wherein like reference numerals refer to the same or similar elements or elements having the same or similar function throughout. The embodiments described below with reference to the drawings are exemplary and intended to be used for explaining the present invention, and should not be construed as limiting the present invention.

A refueling water tank 100 for a nuclear power plant in-containment water replenishment safety system according to a first aspect of the present invention is described below with reference to fig. 1.

According to the utility model discloses a reloading water tank 100 that is used for moisturizing safety coefficient in nuclear power station containment of first aspect, include: a housing 1, a sprinkler 2 and at least one first heat sink 3.

Specifically, a water containing cavity 11 is formed in the housing 1, water is filled in the water containing cavity 11, an injection port 12 may be arranged on the housing 1, the injection port 12 may be communicated with the water containing cavity 11, and one end of the sprinkler 2 (for example, the lower end of the sprinkler 2 shown in fig. 1) extends into the water containing cavity 11; the first heat absorption means 3 comprise at least one, in other words one first heat absorption means 3 can be provided, also a plurality of first heat absorption means 3 can be provided, for example two, three or more first heat absorption means 3 can be provided; the phase change material 32 is arranged in the first heat absorbing device 3, and the first heat absorbing device 3 can be arranged in the water containing cavity 11, so that when the sprinkler 2 sprays a large amount of high-temperature steam and water into the water containing cavity 11 to raise the safety injection water temperature in the water containing cavity 11, the safety injection water temperature can be lowered by the phase change heat absorption of the phase change material 32 by the first heat absorbing device 3, and the safety injection water injected into a reactor pressure vessel (such as a reactor pressure vessel described below) from the water containing cavity 11 is ensured to be in a safe temperature range, so that the long-term submerging and cooling of a reactor core (not shown) in the reactor pressure vessel are realized, the pressure boundary of a fuel rod wrapping radioactive substances is not invalid, and the occurrence of a serious radioactive leakage condition is prevented.

For example, as shown in fig. 1, the housing 1 of the refueling water tank 100 may be formed in a substantially cylindrical shape, a water containing cavity 11 is formed in the housing 1, the height of the liquid level in the water containing cavity 11 may be substantially three-fourths of the height of the water containing cavity 11, a bubbler may be provided below the liquid level of the water containing cavity 11, one end of the sprinkler 2 extends below the liquid level in the water containing cavity 11, and the first heat absorbing device 3 may include: the base member, the base member can form into the cylinder, can be formed with the phase transition chamber in the base member, the phase transition chamber can form into a plurality ofly along the radial inside and outside interval arrangement of base member, and the phase transition intracavity is filled has phase change material 32, like this, can increase the heat transfer area of ann water in first heat sink 3 and the water holding chamber 11, promotes cooling rate.

According to the utility model discloses a reloading water tank 100, through the inside first heat sink 3 that is equipped with phase change material 32 that sets up in holding water cavity 11, make when sprinkler 2 to holding water cavity 11 in spout into steam and water of a large amount of high temperatures and make the ann's notes temperature of holding in the water cavity 11 rise, first heat sink 3 can reduce ann's notes temperature through phase change heat absorption of phase change material 32, guarantee to pour into the ann's notes water of reactor pressure vessel from casing 1 in and be in safe temperature range, thereby realize the long-term flooding and the cooling of the reactor core in the reactor pressure vessel, make the pressure boundary of fuel rod parcel radioactive substance inefficacy, prevent the emergence of the serious radioactive leakage condition.

Alternatively, the phase change material 32 may take various forms, such as inorganic materials (e.g., crystalline hydrated salts, molten salts, etc.), organic materials (e.g., paraffin, acetic acid, polyethylene, fatty acids, esters, alcohols, and partial polymers, etc.), composite materials, etc. Preferably, the phase change material 32 within the first heat sink 3 is a solid-liquid phase change material or a solid-solid phase change material.

According to some embodiments of the present invention, the first heat absorbing device 3 is located between one end of the sprinkler 2 and the safety injection port 12, so that the high temperature water sprayed in the sprinkler 2 can be rapidly diffused and flow toward the first heat absorbing device 3, and exchange heat with the first heat absorbing device 3 to cool down, then flow toward the safety injection port 12, and finally be discharged through the safety injection port 12. Therefore, the heat absorption efficiency of the first heat absorption device 3 can be ensured, and the safety injection water temperature is effectively reduced. In addition, the water can flow out of the safety injection port 12 smoothly during gravity safety injection.

Alternatively, the first heat absorbing means 3 may be placed near the bubbler in the water containing chamber 11, whereby the rate of lowering the temperature of the first heat absorbing means 3 by the installation water can be increased.

According to the utility model discloses a some embodiments, be formed with heat absorption channel 31 in the first heat absorbing device 3, heat absorption channel 31's export intercommunication is to ann annotates mouth 12, from this, in the spun high temperature water can the rapid diffusion and flow into heat absorption channel 31 in sprinkler 2, carries out the heat transfer cooling with the phase change material in the first heat absorbing device 3, and the ann water injection after the heat absorption cooling of first heat absorbing device 3 can directly flow from ann annotating mouth 12, prevents to flow back to holding in the water cavity 11 through the ann water injection of cooling. In addition, since the outlet of the heat absorbing channel 31 is communicated to the safety injection port 12, if the water in the refueling water tank 100 flows to the safety injection port 12, the water must flow through the heat absorbing channel 31 first, so that the water in the refueling water tank 100 can be ensured to exchange heat with the phase change material 32 in the first heat absorbing device 3 through the heat absorbing channel 31 sufficiently, the heat exchange efficiency is improved, and the safety injection water temperature is effectively reduced.

Furthermore, the cross-sectional area of any cross-section of the heat absorption channel 31 is larger than the cross-sectional area of the safety injection port 12, so that on one hand, the surface area of the heat absorption channel 31 is increased, the phase change heat exchange area of the first heat absorption device 3 is increased, the cooling rate and efficiency of the safety injection water are improved, and on the other hand, the cooled safety injection water can smoothly and fully flow out of the safety injection port 12. For example, as shown in fig. 1, the heat absorbing passage 31 may be formed as a circular truncated cone-shaped passage, and the cross-sectional area of the heat absorbing passage 31 gradually increases in the direction from the top to the bottom, and the cross-sectional area of the upper end of the heat absorbing passage 31 is larger than the cross-sectional area of the pour opening 12. It should be noted that, the cross-sectional area of the inlet of the heat absorption channel 31 is larger than the cross-sectional area of the safety injection opening 12, so that sufficient safety injection water in the heat absorption channel 31 can be ensured to be discharged from the safety injection opening 12 all the time, and the water injection efficiency of the safety injection opening 12 is improved as much as possible.

According to some embodiments of the present invention, a horizontally extending bottom plate 13 is disposed in the housing 1, the bottom plate 13 is disposed near the bottom wall of the housing 1, for example, as shown in fig. 1, the bottom plate 13 can be located on the upper side of the bottom wall, the first heat absorbing device 3 is fixed on the bottom plate 13, and the first heat absorbing device 3 is located below one end of the sprinkler 2 (for example, the lower end of the sprinkler 2 shown in fig. 1), thereby, the bottom plate 13 in this embodiment can facilitate the fixing of the first heat absorbing device 3, and at the same time, it is convenient for the safety injection water in the refueling water tank 100 to smoothly flow out from the safety injection port 12 during gravity safety injection.

Further, the first heat absorbing device 3 is detachably connected with the bottom plate 13, so that the first heat absorbing device 3 can be conveniently overhauled and replaced, and the parameter performance of the first heat absorbing device 3 can be adjusted by replacing the phase change material 32, so that the application range of the first heat absorbing device 3 is wider.

According to some embodiments of the present invention, the phase change temperature of the phase change material 32 is in the range of 40 ℃ to 90 ℃. For example, the phase change temperature of the phase change material 32 may be 40 ℃, 50 ℃, 60 ℃, 70 ℃, 80 ℃ or 90 ℃. For example, when the phase change temperature of the phase change material 32 arranged in the first heat absorbing device 3 is 50 ℃, in the steady-state operation process of the nuclear power plant, the phase change material 32 does not undergo phase change heat absorption because the water temperature does not reach 50 ℃, after the automatic pressure reduction system is started in an accident, a large amount of high-temperature water and steam are sprayed into the refueling water tank 100 through the automatic pressure reduction system, so that when the safety injection water temperature is higher than 50 ℃, the phase change material 32 in the first heat absorbing device 3 undergoes phase change to absorb a large amount of heat, meanwhile, the temperature change of the phase change material 32 is small, the temperature does not continuously rise until the phase change material 32 completes all phase changes, the rise of the water temperature in the refueling water tank 100 is delayed for a long time through the heat storage of the phase change material 32, the water temperature in the safety injection of the refueling water tank 100 is reduced, and the liquid level and the cooling performance in the reactor, the safety of the nuclear power station is improved.

In some embodiments of the present invention, a plurality of heat transfer ribs are disposed on the heat transfer surface of the first heat absorbing device 3 (one side of the heat transfer surface is filled with water, the other side is the phase change material 32, the phase change material 32 and the filled water exchange heat through the heat transfer surface, for example, the inner peripheral wall of the heat absorbing channel 31), so as to increase the heat exchange area between the first heat absorbing device 3 and the filled water, and increase the cooling rate of the filled water. For example, a plurality of heat transfer ribs arranged at intervals may be directly provided on the heat transfer surface of the first heat absorbing means 3, and of course, a metal mesh may be arranged inside the first heat absorbing means 3 to form the heat transfer ribs.

In addition, the present invention is not limited thereto, and various other heat transfer enhancement methods can be adopted to enhance the heat transfer efficiency of the first heat absorbing device 3, for example, to increase the heat transfer surface of the first heat absorbing device 3, and for example, to improve the heat transfer performance of the first heat absorbing device 3 by doping metal particles or adding graphite during the formation process of the matrix of the first heat absorbing device 3.

According to some embodiments of the utility model, can be equipped with phase change material 32 in the first heat sink 3, phase change material 32 is suitable for and holds the gaseous or liquid in the water cavity 11 and take place endothermic reaction to be convenient for in time for ann's water injection cooling when the temperature risees in the reloading water tank 100.

According to some embodiments of the present invention, the first heat absorbing means 3 may also be configured to deposit the phase change material 32 into the refill water tank 100 when the refill water tank 100 reaches a heat absorbing condition. That is to say, when the condition in the refueling water tank 100 reaches the heat absorption condition, for example, the safety water injection temperature in the refueling water tank 100 reaches the set water temperature, the first heat absorbing device 3 may put the phase change material 32 into the refueling water tank 100, and the phase change material 32 may perform a heat absorption chemical reaction with water, so as to absorb the heat of the safety water and achieve the purpose of cooling. For example, the phase change material 32 may be ammonium salt, the ammonium salt is placed in the first heat absorbing device 3, the ammonium salt is added when the temperature in the refueling water tank 100 reaches a predetermined temperature, the ammonium salt is dissolved in water to generate water desorption heat, the temperature of the water in the water containing cavity 11 is reduced, and the ammonium salt is dissolved in water, so that the volume of the water containing cavity 11 is not occupied.

Of course, the present invention is not limited thereto, and the first heat sink 3 can take various forms, for example, the phase change material 32 can be mixed with the base material of the first heat sink 3 to form the first heat sink 3, so that the two are firmly combined into a stable phase change device.

A water replenishment safety system for use in a nuclear power plant containment according to a second aspect of the present invention is described below.

According to the utility model discloses a moisturizing safety coefficient for in nuclear power station containment of second aspect, include: containment (not shown), reactor pressure vessel (not shown) and refueling water tank 100 for a nuclear power plant in-containment water replenishment safety system according to the first aspect of the present invention.

Specifically, the reactor pressure vessel is arranged in the containment vessel, the top of the reactor pressure vessel is provided with a pressure relief port, and the lower part of the reactor pressure vessel is provided with a water replenishing port; the refueling water tank 100 is arranged in the containment, wherein the other end of the sprinkler 2, which is positioned outside the shell 1, is communicated with a pressure relief port, and the safety injection port 12 is communicated with a water replenishing port, so that when a large amount of high-temperature and high-pressure steam or water is generated in the reactor pressure vessel, the high-temperature steam and water can be discharged into the refueling water tank 100 through the pressure relief port in time and cooled through the first heat absorbing devices 3, and the safety injection water which is cooled and has the temperature within a safety range can flow out of the refueling water tank 100 again through the safety injection port 12 and flow back to the reactor pressure vessel through the water replenishing port, thereby ensuring that enough low-temperature water is always filled in the reactor pressure vessel to submerge and cool the reactor core, avoiding the pressure boundary failure of radioactive substances wrapped by the fuel rods, and preventing serious radioactive leakage.

According to the utility model discloses a moisturizing safety coefficient through setting up the refueling water tank 100 that is used for the moisturizing safety coefficient in the nuclear power station containment of above-mentioned first aspect, can be for continuously providing microthermal ann's water injection in the reactor pressure vessel, delay reactor pressure vessel's intensification and step up to reduce the probability that the radioactivity leaked the occurence of failure.

According to the utility model discloses a some embodiments, moisturizing safety coefficient still includes: at least one second heat sink (not shown) disposed within the containment vessel for absorbing heat from the gas or liquid within the containment vessel. In other words, the second heat sink may include one or more, the one or more second heat sinks may be disposed in the containment and outside the refueling water tank 100, and the plurality of second heat sinks are used for absorbing heat of gas or liquid in the containment, so that the temperature and pressure in the containment are in a safe range.

Furthermore, the second heat absorption device is a phase change heat absorption device, and the phase change material is filled in the second heat absorption device. Therefore, the second heat absorption device can perform a phase change heat absorption process with high-temperature gas or liquid in the containment vessel, the temperature of the containment vessel is reduced, the temperature rise and the pressure rise of the reactor pressure vessel are delayed, and the occurrence probability of radioactive leakage accidents is reduced.

It is understood that the phase change material in the second heat absorbing means can take various forms, such as inorganic materials (e.g., crystalline hydrated salts, molten salts, etc.), organic materials (e.g., paraffin, acetic acid, polyethylene, fatty acids, esters, alcohols, and partial polymers, etc.), composite materials, etc. Preferably, the phase change material within the second heat sink is a solid-liquid phase change material or a solid-solid phase change material.

It will be appreciated that the parametric properties of the second heat sink can be adjusted by replacement of the phase change material, resulting in a wider range of applicability of the second heat sink.

According to some embodiments of the present invention, the second heat sink may have a plurality of heat transfer ribs on a heat transfer surface thereof. Therefore, the heat exchange area between the second heat absorption device and the gas or liquid in the containment can be increased, and the cooling and pressure reduction rate of the containment is improved.

According to some embodiments of the utility model, the phase transition temperature of the phase change material in the second heat sink is less than the saturation temperature that the design pressure of containment corresponds. For example, when the saturation temperature of the containment is 25 ℃, the phase change temperature of the phase change material 32 may be 18 ℃, 20 ℃ or 22 ℃, so that when an accident occurs, if the temperature in the containment rises to the phase change temperature, the second heat sink may absorb a large amount of heat of water and steam in the containment, so that the temperature rise and pressure rise rate in the containment is greatly reduced, and the possibility of overpressure failure of the containment is avoided; when the pressure and the temperature in the containment vessel are reduced to the phase change temperature of the phase change material in the middle and later period of an accident, the latent heat of phase change starts to be released, the core decay heat is lower at the moment, the safety margin of the containment vessel is very high, and the phase change heat release at the moment can not cause damage to the boundary integrity of the containment vessel.

According to some embodiments of the present invention, the second heat sink may be further configured to deposit a phase change material into the containment vessel when the temperature in the containment vessel reaches a heat sink condition. That is to say, when the temperature of water in the containment reaches the heat absorption condition, the second heat absorption device can put phase change material into the containment, and the phase change material can react with water chemically to absorb the heat of the arranged water, thereby achieving the purpose of cooling. If the ammonium salt is placed in the second heat absorption device, the ammonium salt is put into the containment when the temperature in the containment reaches the preset temperature, the ammonium salt is dissolved in water to generate water desorption heat so as to reduce the water temperature in the containment, reduce steam and relieve the pressure rise rate in the containment, and the ammonium salt is dissolved in water so as not to occupy the volume in the containment. Alternatively, a valve may be provided on the second heat sink, and after the automatic depressurization system is turned on, the phase change material is dispensed by opening the valve, thereby triggering the endothermic chemical reaction to be turned on.

Optionally, the second heat sink disposed in the gas space inside the containment may also be disposed at the outlet of the steam source of the automatic depressurization system to absorb heat in the hot steam in time.

In addition, the first heat absorbing device 3 arranged in the refueling water tank 100 and the second heat absorbing device arranged in the containment vessel can indirectly push up the liquid level in the reactor pressure vessel and improve the gravity head.

In the description of the present invention, it is to be understood that the terms "center", "longitudinal", "lateral", "length", "width", "thickness", "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", "clockwise", "counterclockwise", "axial", "radial", "circumferential", and the like, indicate the orientation or positional relationship based on the orientation or positional relationship shown in the drawings, and are only for convenience of description and simplicity of description, and do not indicate or imply that the device or element referred to must have a particular orientation, be constructed and operated in a particular orientation, and therefore, should not be construed as limiting the present invention.

Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include one or more of that feature. In the description of the present invention, "a plurality" means two or more unless specifically limited otherwise.

In the present invention, unless otherwise expressly stated or limited, the terms "mounted," "connected," and "fixed" are to be construed broadly and may, for example, be fixedly connected, detachably connected, or integrally formed; the connection can be mechanical connection, electrical connection or communication; either directly or indirectly through intervening media, either internally or in any other relationship. The specific meaning of the above terms in the present invention can be understood according to specific situations by those skilled in the art.

In the description herein, references to the description of the term "one embodiment," "some embodiments," "an example," "a specific example," or "some examples," etc., mean that a particular feature, structure, material, or characteristic described in connection with the embodiment or example is included in at least one embodiment or example of the invention. In this specification, the schematic representations of the terms used above are not necessarily intended to refer to the same embodiment or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments or examples. Furthermore, various embodiments or examples and features of different embodiments or examples described in this specification can be combined and combined by one skilled in the art without contradiction.

While embodiments of the present invention have been shown and described, it will be understood by those of ordinary skill in the art that: various changes, modifications, substitutions and alterations can be made to the embodiments without departing from the principles and spirit of the invention, the scope of which is defined by the claims and their equivalents.

Claims (14)

1. A refueling water tank for a water replenishing safety system in a nuclear power station containment is characterized by comprising:

the device comprises a shell, a water storage cavity is arranged in the shell, and a safety injection port communicated with the water storage cavity is arranged on the shell;

the sprinkler is provided with one end extending into the water containing cavity;

the phase change material is arranged in the first heat absorption device, and the first heat absorption device is arranged in the water containing cavity.

2. The refueling water tank for a nuclear power plant in-containment refueling safety system as recited in claim 1 wherein the first heat sink is located between the one end of the sprinkler and the pour spout.

3. The refueling water tank for the water replenishing safety system in the nuclear power station containment vessel as claimed in claim 1, wherein a heat absorption channel is formed in the first heat absorption device, and an outlet of the heat absorption channel is communicated to the safety injection port.

4. The refueling water tank for the water replenishing safety system in the nuclear power station containment vessel as recited in claim 3, wherein the cross-sectional area of any section of the heat absorbing channel is larger than the cross-sectional area of the injection port.

5. The refueling water tank for a nuclear power plant in-containment refueling safety system as recited in claim 1 wherein a horizontally extending floor is provided within the housing, the floor being disposed adjacent a bottom wall of the housing, the first heat sink being secured to the floor and being positioned below the one end of the sprinkler.

6. The refueling water tank for the nuclear power plant in-containment refueling safety system as recited in claim 5 wherein the first heat sink is removably attached to the bottom plate.

7. The refueling water tank for the nuclear power plant in-containment water replenishing safety system according to claim 1, wherein the phase change temperature of the phase change material is in a range of 40 ℃ to 90 ℃.

8. The refueling water tank for the water replenishing safety system in the nuclear power station containment according to claim 1, wherein a plurality of heat transfer ribs are arranged on the heat transfer surface of the first heat absorbing device.

9. The refueling water tank for the nuclear power plant containment water replenishing safety system according to claim 1, wherein the phase change material adapted to perform an endothermic reaction with a gas or liquid in the water containing cavity is arranged in the first heat absorbing device.

10. The refueling water tank for a nuclear power plant in-containment refueling safety system as recited in claim 9 wherein the first heat sink is configured to deposit the phase change material into the water containing cavity when the refueling water tank reaches a heat sink condition.

11. A water replenishing safety system used in a nuclear power station containment is characterized by comprising:

the containment vessel is provided with a safety shell,

the reactor pressure vessel is arranged in the containment vessel, the top of the reactor pressure vessel is provided with a pressure relief opening, and the lower part of the reactor pressure vessel is provided with a water replenishing opening;

the refueling water tank for the water replenishing safety system in the nuclear power station containment is arranged in the containment according to any one of claims 1 to 10,

the other end of the sprayer, which is positioned outside the shell, is communicated with the pressure relief port, and the injection port is communicated with the water replenishing port.

12. The water replenishment safety system for use in a nuclear power plant containment vessel of claim 11 further comprising: and the second heat absorption device is arranged in the containment and is used for absorbing the heat of the gas or the liquid in the containment.

13. The water replenishing safety system for use in a nuclear power plant containment vessel as recited in claim 12, wherein the second heat sink is a phase change heat sink filled with a phase change material.

14. The water replenishing safety system for the nuclear power plant containment vessel as recited in claim 13, wherein the phase change temperature of the phase change material in the second heat sink is less than a saturation temperature corresponding to a design pressure of the containment vessel.

Images