De-foaming device for water outlet of nuclear power station

Abstract

The utility model discloses a nuclear power station water outlet defoaming device which comprises an outer sleeve, an inner sleeve and a cover plate, the inner sleeve is arranged in the outer sleeve, a liquid guide space is formed between the inner side wall of the outer sleeve and the outer side wall of the inner sleeve, the cover plate is connected with the upper peripheral edge of the outer sleeve and the upper peripheral edge of the inner sleeve, and a liquid inlet hole is formed in the cover plate. The liquid inlet hole is communicated with the liquid guide space; the liquid guide pipe transversely penetrates through the circumferential opposite side walls of the inner sleeve, and a liquid inlet and a liquid outlet are formed in the two ends of the liquid guide pipe respectively; a spraying pipeline is arranged on the upper peripheral edge of the inner sleeve, is provided with a plurality of spray heads, and is connected and communicated with the liquid guide pipe through a connecting pipeline; the defoaming device for the water outlet of the nuclear power plant further comprises a submersible pump connected with the liquid guide pipe, the submersible pump is arranged close to the liquid inlet, and the submersible pump is used for pumping sea water flowing into the liquid guide space to the spraying pipeline and spraying the sea water out of the nozzle so as to defoam the sea water at the water outlet of the nuclear power plant. A physical defoaming mode is adopted, the treatment mode is relatively simple, and the cost is low.

Description

Technical Field

[0001] The utility model relates to the technical field of nuclear power, in particular to a defoaming device for a drain outlet of a nuclear power station. Background Art

[0002] In order to ensure that the heat of the reactor core can be removed in time under different operating conditions, coastal nuclear power plants are usually designed to use seawater as a cooling source. 3 / h. The main component of algae and dead marine organisms in seawater is protein, which has the ability to enhance surface properties, thereby increasing the viscosity of seawater. When water flows into the siphon well and falls, it is accompanied by bubbles rising to the drain outlet. At the same time, algae and dead marine organisms float to the surface to form foam. According to the "Seawater Quality Standard" (GB3097-1997), the sea surface must be free of oil film, foam, and other floating matter. Therefore, it is necessary to dissolve the foam as much as possible. Utility Model Content

[0003] The technical problem to be solved by the utility model is to provide a defoaming device for a drain outlet of a nuclear power plant.

[0004] The technical solution adopted by the utility model to solve the technical problem is as follows: a defoaming device for a drain outlet of a nuclear power plant is constructed, comprising an outer sleeve, an inner sleeve and a cover plate, wherein the inner sleeve is arranged in the outer sleeve and a liquid guide space is formed between the inner side wall of the outer sleeve and the outer side wall of the inner sleeve, the cover plate is annular, the cover plate connects the upper edge of the outer sleeve and the upper edge of the inner sleeve, and the cover plate is provided with a plurality of liquid inlet holes, which are in communication with the liquid guide space;

[0005] The defoaming device for the drain outlet of a nuclear power plant further includes a liquid guide pipe that transversely passes through opposite circumferential side walls of the inner sleeve, with a liquid inlet and a liquid outlet at either end of the liquid guide pipe; a spray pipe is provided on the upper edge of the inner sleeve, the spray pipe is provided with a plurality of nozzles, and the spray pipe is connected and communicated with the liquid guide pipe via a connecting pipe;

[0006] The defoaming device for the drain outlet of a nuclear power plant further comprises a submersible pump connected to the liquid guide pipe, and the submersible pump is arranged close to the liquid inlet.

[0007] In some embodiments, the liquid inlet is provided with a filter.

[0008] In some embodiments, the connecting pipeline is provided with at least one first control valve.

[0009] In some embodiments, the catheter is further provided with a sampling device, and the sampling device is located downstream of the submersible pump.

[0010] In some embodiments, the sampling device includes a COD analyzer, a dissolved oxygen meter, a pH meter, a thermometer and / or a turbidity meter.

[0011] In some embodiments, the fluid conduit is provided with at least one second control valve, and the second control valve is located downstream of the submersible pump.

[0012] In some embodiments, a check valve is further provided upstream of the sampling device.

[0013] In some embodiments, the outer sleeve is coaxially arranged with the inner sleeve.

[0014] In some embodiments, the nuclear power plant drain outlet defoaming device further includes a plurality of floats connected to the outer sleeve.

[0015] In some embodiments, the nuclear power plant drain outlet defoaming device further includes a plurality of counterweights connected to the outer sleeve.

[0016] The implementation of the present invention has the following beneficial effects: the defoaming device for a nuclear power plant drain outlet includes an outer sleeve, an inner sleeve, and a cover plate. The inner sleeve is disposed within the outer sleeve, and a liquid guide space is formed between the inner sidewall of the outer sleeve and the outer sidewall of the inner sleeve. The cover plate is annular and connects the upper edge of the outer sleeve with the upper edge of the inner sleeve. The cover plate is provided with a plurality of liquid inlet holes, which are connected to the liquid guide space. The defoaming device for the nuclear power plant drain outlet also includes a liquid guide pipe that transversely extends through opposite circumferential sidewalls of the inner sleeve, with a liquid inlet and a liquid outlet at each end of the liquid guide pipe. A spray pipe is provided on the upper edge of the inner sleeve, and the spray pipe is provided with a plurality of nozzles. The spray pipe and the liquid guide pipe are connected and communicated via a connecting pipe. The defoaming device for the nuclear power plant drain outlet also includes a submersible pump connected to the liquid guide pipe, disposed near the liquid inlet. The submersible pump is used to pump seawater flowing into the liquid guide space to the spray pipe, where it is sprayed by the nozzles, thereby defoaming the seawater at the nuclear power plant drain outlet. The defoaming device uses a physical defoaming method, which is relatively simple and low-cost. BRIEF DESCRIPTION OF THE DRAWINGS

[0017] In order to more clearly illustrate the technical solution of the present invention, the present invention will be further described below in conjunction with the accompanying drawings and embodiments. It should be understood that the following drawings only illustrate certain embodiments of the present invention and should not be considered as limiting the scope. A person of ordinary skill in the art can derive other relevant drawings based on these drawings without inventive effort. In the drawings:

[0018] Figure 1 This is one of the structural schematic diagrams of the defoaming device for the drain outlet of a nuclear power plant in some embodiments of the present utility model;

[0019] Figure 2This is the second structural schematic diagram of the defoaming device for the drain outlet of a nuclear power plant in some embodiments of the present invention. DETAILED DESCRIPTION

[0020] In order to have a clearer understanding of the technical features, purposes and effects of the present invention, the specific embodiments of the present invention are now described in detail with reference to the accompanying drawings. In the following description, it should be understood that the directions or positional relationships indicated by "front", "back", "up", "down", "left", "right", "longitudinal", "horizontal", "vertical", "horizontal", "top", "bottom", "inside", "outside", "head", "tail", etc. are based on the directions or positional relationships shown in the accompanying drawings and are constructed and operated in specific directions. They are only for the convenience of describing the present technical solution and do not indicate that the devices or components referred to must have specific directions. Therefore, they should not be understood as limiting the present invention.

[0021] It should also be noted that, unless otherwise clearly specified and limited, terms such as "installed", "connected", "connected", "fixed", and "set" should be understood in a broad sense. For example, they can be fixedly connected, detachably connected, or integrated; they can be mechanically connected or electrically connected; they can be directly connected or indirectly connected through an intermediate medium, and they can be internal connections between two elements or interactions between two elements. When an element is referred to as being "on" or "under" another element, the element can be "directly" or "indirectly" located on the other element, or there may be one or more intervening elements. The terms "first", "second", and "third" are only used to facilitate the description of the present technical solution and cannot be understood as indicating or implying relative importance or implicitly indicating the number of the indicated technical features. Therefore, features defined as "first", "second", and "third" can explicitly or implicitly include one or more of these features. For those of ordinary skill in the art, the specific meanings of the above terms in the present utility model can be understood according to specific circumstances.

[0022] In the following description, specific details such as specific system structures and techniques are provided for purposes of illustration, not limitation, to facilitate a thorough understanding of the embodiments of the present invention. However, it will be apparent to those skilled in the art that the present invention may be implemented in other embodiments without these specific details. In other cases, detailed descriptions of well-known systems, devices, circuits, and methods are omitted to avoid obscuring the description of the present invention with unnecessary detail.

[0023] See Figure 1 and Figure 2 The utility model shows a defoaming device for a nuclear power plant drain outlet, which is used to be installed at the drain outlet of the nuclear power plant and is used for defoaming seawater at the drain outlet of the nuclear power plant.

[0024] The defoaming device for the drain outlet of a nuclear power plant includes an outer sleeve 10, an inner sleeve 20 and a cover plate 30. The inner sleeve 20 is arranged in the outer sleeve 10 and a liquid guide space A is formed between the inner wall of the outer sleeve 10 and the outer wall of the inner sleeve 20. The cover plate 30 is annular and connects the upper edge of the outer sleeve 10 and the upper edge of the inner sleeve 20. A plurality of liquid inlet holes 31 are provided on the cover plate 30. The liquid inlet holes 31 may include but are not limited to circular holes. The number of the liquid inlet holes 31 may be 6 to 8, and the plurality of liquid inlet holes 31 are arranged at intervals. The liquid inlet holes 31 are connected to the liquid guide space A.

[0025] The nuclear power plant drain outlet defoaming device also includes a liquid conduit 40 extending transversely through opposite circumferential sidewalls of the inner sleeve 20. The conduit 40 has a liquid inlet 41 and a liquid outlet 42 at either end. A spray pipe 50 is provided on the upper edge of the inner sleeve 20. The spray pipe 50 is equipped with a plurality of spray nozzles 51. The spray pipe 50 is connected to and communicates with the conduit 40 via a connecting pipe 60. The nuclear power plant drain outlet defoaming device also includes a submersible pump 70 connected to the conduit 40. The submersible pump 70 is positioned near the liquid inlet 41 and is used to pump seawater flowing into the liquid conduit space A into the spray pipe 50 for spraying by the spray nozzles 51, thereby defoaming the seawater at the nuclear power plant drain outlet.

[0026] The outer sleeve 10 and the inner sleeve 20 can both be circular cylindrical structures, and the outer sleeve 10 is coaxially arranged with the inner sleeve 20. Furthermore, the defoaming device for the drain outlet of a nuclear power plant also includes a plurality of buoys 11 connected to the outer sleeve 10. The buoys 11 can be directly fixed to the outer sleeve 10 or connected by a chain, or the outer sleeve 10 is connected to the dam of the drain outlet of the nuclear power plant by a connecting cable. Preferably, the buoys 11 can be made of polyethylene, high-density polyethylene or ultra-high molecular weight polyethylene. Of course, the shape, size and material of the buoys 11 can be selected and set according to actual needs, and are not specifically limited here.

[0027] The nuclear power plant drain outlet defoaming device further includes a plurality of counterweights 12 connected to the outer sleeve 10. The counterweights 12 may be mounted on the outer wall of the outer sleeve 10 near the bottom, or alternatively, on the bottom of the outer sleeve 10. The counterweights 12 may improve the stability of the nuclear power plant drain outlet defoaming device and prevent it from swaying due to waves.

[0028] The counterweight 12 can be made of concrete. The counterweight 12 can be connected to the outer sleeve 10 via a connecting rope or a buckle. For example, the counterweight 12 can have a first connecting lug, and the outer sleeve 10 can have a second connecting lug, with a connecting rope connecting the first and second connecting lugs.

[0029] In some embodiments, the outer sleeve 10 and the inner sleeve 20 may be made of high-density polyethylene (HDPE), a highly crystalline, non-polar thermoplastic resin produced by copolymerization of ethylene. Raw HDPE has a milky white appearance and is somewhat translucent in thin cross-sections. It exhibits excellent resistance to most household and industrial chemicals, including corrosion and dissolution by strong oxidants (concentrated nitric acid), acids, bases, salts, and organic solvents (carbon tetrachloride). It is suitable for use in marine environments. Of course, the cover plate 30 may also be made of high-density polyethylene.

[0030] In some embodiments, the outer sleeve 10 and the inner sleeve 20 may be made of ultra-high molecular weight polyethylene (UHMWPE), also known as high-strength and high-modulus polyethylene (HMPE). This is unbranched, linear polyethylene with a molecular weight of 1.5 million or more. UHMWPE exhibits excellent mechanical properties, impact resistance, wear resistance, chemical resistance, and optical resistance. The cover plate 30 may also be made of UHMWPE.

[0031] In some embodiments, the outer sleeve 10 , the inner sleeve 20 and the cover plate 30 may also be made of stainless steel.

[0032] In some embodiments, the outer sleeve 10 may have a diameter of 2 to 5 meters, and the inner sleeve 20 may have a diameter of 2 to 4 meters. For example, the outer sleeve 10 may have a diameter of 4 meters, and the inner sleeve 20 may have a diameter of 3 meters.

[0033] It can be understood that the shapes, sizes and materials of the outer sleeve 10, the inner sleeve 20 and the cover plate 30 can be selected and set according to actual needs and are not specifically limited here.

[0034] In some embodiments, the liquid inlet 31 is equipped with a filter to prevent marine organisms or impurities from directly entering the liquid-conducting space A. The filter can also perform appropriate defoaming operations. The filter can include, but is not limited to, a copper alloy mesh or a high-strength zinc-aluminum alloy mesh. Alternatively, the filter can be a polyethylene mesh with the following specifications: a 60-wire warp knitted mesh with a mesh size of 30 mm, a 60-wire warp knitted mesh with a mesh size of 40 mm, or a 60-wire warp knitted mesh with a mesh size of 50 mm.

[0035] In some embodiments, the connecting pipe 60 is provided with at least one first control valve 61 , and the first control valve 61 can be a ball valve.

[0036] In some embodiments, the drainage tube 40 is further provided with a sampling device 80, which is located downstream of the submersible pump 70. The sampling device 80 can be used to sample the drainage water to enable real-time monitoring of water quality. The sampling device 80 can be connected to the onshore control platform via a wired or wireless connection. When a wired connection is used, the connection can be via a waterproof armored cable.

[0037] The sampling device 80 includes a COD analyzer, a dissolved oxygen meter, a pH meter, a thermometer, and / or a turbidity meter. Appropriate instruments and combinations thereof can be selected according to actual needs to detect seawater at the nuclear power plant outlet.

[0038] Among them, COD analyzer (abbreviation of chemical oxygen demand), the Chinese name is "chemical oxygen demand" or "chemical oxygen consumption", which refers to the amount of oxygen consumed by the oxidation and decomposition of reducing substances (such as organic matter) in water using chemical oxidants (such as potassium dichromate). It reflects the degree of pollution of the water body by reducing substances. The dissolved oxygen meter is a device for measuring dissolved oxygen in water. The working principle is that oxygen passes through the diaphragm and is reduced by the working electrode, generating a diffusion current proportional to the oxygen concentration. By measuring this current, the concentration of dissolved oxygen in the water is obtained. The pH meter, also known as the pH meter, is an instrument for measuring pH value, also known as the pH meter and acid-base detector. The turbidity meter, also known as the turbidity meter, is used to detect the turbidity of seawater.

[0039] In some embodiments, the liquid conduit 40 is provided with at least one second control valve 43, and the second control valve 43 is located downstream of the submersible pump 70. The second control valve 43 can also be provided downstream of the sampling device 80.

[0040] In some embodiments, a check valve 44 is further provided upstream of the sampling device 80 to prevent backflow of seawater.

[0041] It can be understood that the defoaming device at the drain outlet of the nuclear power plant adopts a physical defoaming method, which is relatively simple and low in cost.

[0042] It can be understood that the above embodiments only express the preferred implementation methods of the present invention, and the descriptions thereof are relatively specific and detailed, but they cannot be understood as limiting the patent scope of the present invention. It should be pointed out that for ordinary technicians in this field, without departing from the concept of the present invention, the above technical features can be freely combined, and several deformations and improvements can be made, all of which fall within the scope of protection of the present invention. Therefore, all equivalent changes and modifications made to the scope of the claims of the present invention should fall within the scope of coverage of the claims of the present invention.

Claims

1. A defoaming device for a nuclear power plant drain outlet, characterized in that: The invention comprises an outer sleeve (10), an inner sleeve (20) and a cover plate (30), wherein the inner sleeve (20) is arranged in the outer sleeve (10) and a liquid guide space (A) is formed between the inner side wall of the outer sleeve (10) and the outer side wall of the inner sleeve (20), and the cover plate (30) is annular, and the cover plate (30) connects the upper edge of the outer sleeve (10) and the upper edge of the inner sleeve (20), and a plurality of liquid inlet holes (31) are provided on the cover plate (30), and the liquid inlet holes (31) are communicated with the liquid guide space (A); The defoaming device for the drain outlet of a nuclear power plant further comprises a liquid guide tube (40) which passes through opposite circumferential side walls of the inner sleeve (20) in a transverse direction, and the two ends of the liquid guide tube (40) are respectively a liquid inlet (41) and a liquid outlet (42); a spray pipe (50) is provided on the upper edge of the inner sleeve (20), and the spray pipe (50) is provided with a plurality of spray heads (51); the spray pipe (50) and the liquid guide tube (40) are connected and communicated through a connecting pipe (60); The nuclear power plant drain outlet defoaming device further comprises a submersible pump (70) connected to the liquid guide pipe (40), and the submersible pump (70) is arranged close to the liquid inlet (41).

2. The defoaming device for the drain outlet of a nuclear power plant according to claim 1, characterized in that: The liquid inlet (31) is provided with a filter screen.

3. The defoaming device for the drain outlet of a nuclear power plant according to claim 1, characterized in that: The connecting pipe (60) is provided with at least one first control valve (61).

4. The defoaming device for the drain outlet of a nuclear power plant according to claim 1, characterized in that: The liquid guiding tube (40) is further provided with a sampling device (80), and the sampling device (80) is located downstream of the submersible pump (70).

5. The defoaming device for the drain outlet of a nuclear power plant according to claim 4, characterized in that: The sampling device (80) includes a COD analyzer, a dissolved oxygen meter, a pH meter, a thermometer and / or a turbidity meter.

6. The defoaming device for the drain outlet of a nuclear power plant according to claim 4, characterized in that: The liquid conduit (40) is provided with at least one second control valve (43), and the second control valve (43) is located downstream of the submersible pump (70).

7. The defoaming device for the drain outlet of a nuclear power plant according to claim 4, characterized in that: A check valve (44) is also provided upstream of the sampling device (80).

8. The defoaming device for a nuclear power plant drain outlet according to claim 1, characterized in that: The outer sleeve (10) and the inner sleeve (20) are coaxially arranged.

9. The defoaming device for a nuclear power plant drain outlet according to claim 1, characterized in that: The nuclear power plant drain outlet defoaming device further comprises a plurality of floats (11) connected to the outer sleeve (10).

10. The defoaming device for a nuclear power plant drain outlet according to claim 1, characterized in that: The nuclear power plant drain outlet defoaming device further comprises a plurality of counterweights (12) connected to the outer sleeve (10).

Images