Nuclear power helium compressor isolation and pressure maintaining maintenance device

By incorporating a turbulence-inducing structure and a limiting shell into the isolation and pressure-maintaining maintenance device for nuclear power helium compressors, the problem of uneven cooling was solved, achieving uniform cooling of high-temperature gases and improving the cooling efficiency of the helium compressors.

CN223524404UActive Publication Date: 2025-11-07CHINA STATE SHIPBUILDING CORP LTD RESEARCH INSTITUTE 719
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Patent Information

Application Number
CN202422873612.3
Authority / Receiving Office
CN · China
Patent Type
Utility models(China)
Current Assignee / Owner
Filing Date
2024-11-22
Publication Date
2025-11-07
Estimated Expiration
2034-11-22

AI Technical Summary

Technical Problem

During the cooling process of the existing nuclear power plant helium compressor isolation and pressure maintenance device, the high-pressure gas temperature is higher in the area far from the inner wall of the container, resulting in uneven cooling and affecting the cooling efficiency of the compressor.

Method used

A turbulence-disrupting structure is installed on the pressure vessel shell, including a first impeller, a turbulence-disrupting component, and a drive shaft. Cooling water circulates from bottom to top, impacting the first impeller to make it rotate. The drive shaft drives the turbulence-disrupting component to disturb the high-temperature gas pressure inside the pressure vessel shell. Combined with the design of a limiting shell and a one-way valve, uniform cooling of the high-temperature gas is achieved.

Benefits of technology

This achieves uniform cooling of the high-temperature gas pressure inside the pressure vessel cylinder, enhances the cooling effect of the helium compressor, and improves cooling efficiency.

✦ Generated by Eureka AI based on patent content.

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Abstract

The utility model discloses a nuclear power helium compressor isolating and pressure maintaining overhauling device, which relates to the technical field of compressor overhauling equipment, and comprises a pressure vessel barrel and a jacket barrel which are arranged inside and outside, a cooling channel is formed between the pressure vessel barrel and the jacket barrel, and turbulent flow structures are uniformly distributed on the pressure vessel barrel. The turbulent flow structure comprises a first impeller, a turbulent flow piece and a transmission shaft, the transmission shaft penetrates through the pressure vessel barrel and is rotationally installed on the pressure vessel barrel in a sealed mode, the first impeller is located between the pressure vessel barrel and the jacket barrel and fixed to one end of the transmission shaft, and the turbulent flow piece is installed at the end, located on the inner side of the pressure vessel barrel, of the transmission shaft; cooling water in the cooling channel impacts the first impeller in the process of circulating from bottom to top so that the first impeller can rotate, and the first impeller drives the spoiler through the transmission shaft to disturb high-temperature air pressure on the inner side of the pressure vessel barrel so that the high-temperature air pressure on the inner side of the pressure vessel barrel can be evenly cooled.
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Description

TECHNICAL FIELD

[0001] The utility model relates to the technical field of compressor overhauling equipment, in particular to a nuclear power helium compressor isolation pressure maintaining overhauling device. BACKGROUND

[0002] The helium compressor is a driving unit of a cryogenic pump system or other refrigeration unit, and is used to provide high-purity helium to the cryogenic pump or other refrigeration unit. The helium compressor generally needs to be periodically overhauled during use, which requires a special helium compressor isolation pressure maintaining overhauling device.

[0003] Regarding the helium compressor isolation pressure maintaining overhauling device, through retrieval, for example, a high-temperature gas cooled reactor helium compressor isolation pressure maintaining overhauling device provided in patent publication No. CN212338148U, when the reactor is normally operated, the screw lifting overhauling device in the overhauling device is built in the helium atmosphere at the upper part of the pressure vessel. When maintenance is needed, the overhauling device lowers the helium compressor to the lower limit position, the pressure maintaining overhauling isolation valve is closed, the pressure boundary of the primary loop is reestablished, and the components to be maintained are isolated outside for maintenance; after the maintenance is completed, the helium compressor that has been overhauled is jacked up by the screw lifting overhauling device, is tightly pressed against the upper sealing surface to achieve the pre-tightening force to realize sealing; the screw lifting overhauling device is driven by a motor and a speed reducer, and is lifted along the guide rails with self-locking function that are uniformly arranged on the inner wall; the jacket cooling system exchanges heat with the metal wall of the equipment, cools the environment in the equipment, and maintains the local low-temperature helium environment to prevent the insulation of the stator winding of the helium compressor and the failure of the speed reducer.

[0004] However, in the static heat exchange process of the above-mentioned helium compressor isolation pressure maintaining overhauling device using cooling water to cool the inner wall of the container, only the high-pressure gas close to the inner wall of the container can be kept at a low temperature, and the high-pressure gas far from the inner wall of the container and close to the compressor side is still relatively high in temperature, and the cooling effect on the compressor needs to be improved. Therefore, a nuclear power helium compressor isolation pressure maintaining overhauling device is proposed to improve the above-mentioned problems. UTILITY MODEL CONTENTS

[0005] The purpose of the present application is to provide a nuclear power helium compressor isolation pressure maintaining overhauling device to solve the problems raised in the background art.

[0006] To achieve the above-mentioned purpose, the present application provides the following technical solution: a nuclear power helium compressor isolation pressure maintaining overhauling device, comprising an inner and outer pressure vessel cylinder and a jacket cylinder, a cooling channel is formed between the pressure vessel cylinder and the jacket cylinder, and a cooling water outlet and a cooling water inlet are arranged at the upper and lower ends of the jacket cylinder, respectively:

[0007] The pressure vessel cylinder is uniformly distributed with a turbulence structure, and the turbulence structure comprises a first impeller, a turbulence piece and a transmission shaft.

[0008] The transmission shaft penetrates the pressure container barrel and is sealingly rotatably installed on the pressure container barrel, the first impeller is located between the pressure container barrel and the jacket barrel and is fixed to one end of the transmission shaft, and the spoiler is installed on the end of the transmission shaft inside the pressure container barrel.

[0009] The cooling water in the cooling channel impacts the first impeller to make the first impeller rotate in the process of circulating from bottom to top, and the first impeller drives the spoiler to disturb the high-temperature gas pressure inside the pressure container barrel through the transmission shaft, so that the high-temperature gas pressure inside the pressure container barrel is uniformly cooled.

[0010] As a further supplement to the scheme, the spoiler is a second impeller.

[0011] As a further supplement to the scheme, the spoiler comprises a limiting shell, a sliding block and a reciprocating screw rod.

[0012] The limiting shell is fixed to the inner wall of the pressure container barrel, the end of the transmission shaft inside the pressure container barrel is coaxially fixed with the reciprocating screw rod, the sliding block is slidingly installed inside the limiting shell, and the middle part of the sliding block is provided with a reciprocating shaft sleeve matched with the reciprocating screw rod.

[0013] The end of the limiting shell away from the pressure container barrel is provided with a gas hole one, the end of the limiting shell close to the pressure container barrel is provided with an exhaust hole, the sliding block is provided with a gas hole two, and the gas hole two and the gas hole one are provided with one-way air valves, the one-way air valve in the gas hole one allows air to enter the inside of the limiting shell, and the one-way air valve in the gas hole two allows air to enter the side of the sliding block close to the pressure container barrel.

[0014] As a further supplement to the scheme, a plurality of partition plates are fixed between the pressure container barrel and the jacket barrel, and the spoiler structure is located between two adjacent partition plates.

[0015] As a further supplement to the scheme, the side end of the partition plate is fixed with a flow guide plate, and the end of the flow guide plate away from the partition plate is obliquely upwardly inclined.

[0016] As a further supplement to the scheme, the inner bottom end of the pressure container barrel is provided with a lifting driving device, the top output end of the lifting driving device is provided with a fixing seat, and the upper end of the fixing seat is placed and fixed with a helium compressor.

[0017] In summary, the technical effects and advantages of the utility model are as follows:

[0018] 1. The utility model discloses a pressure vessel cylinder is provided with the turbulence structure that includes first impeller, spoiler and transmission shaft, and the cooling water in cooling channel is circulated from bottom to top and impacts first impeller to make first impeller rotate in the process, and first impeller drives spoiler through transmission shaft and disturbs the high temperature gas pressure of pressure vessel cylinder inside to make the high temperature gas pressure of pressure vessel cylinder inside receive uniform cooling.

[0019] 2. The utility model discloses a first impeller, transmission shaft, reciprocating screw, sliding block, limit casing and the cooperation and arrangement of one way air valve can realize that the high temperature gas in the middle part of pressure vessel cylinder is guided to the inner wall of pressure vessel cylinder and receives cooling constantly, and the cooling effect of helium compressor is enhanced. ACCURACY

[0020] In order to more clearly illustrate the technical scheme in the embodiment of the present application or prior art, the drawings needed to be used in the embodiment or prior art description will be briefly introduced below, and obviously, the drawings in the following description are only some embodiments of the present application, and other drawings can be obtained by those skilled in the art without creative labor on the premise of these drawings.

[0021] Fig. 1 It is the structure schematic drawing of nuclear power helium compressor isolation pressure maintaining overhauling device in this embodiment 1.

[0022] Fig. 2 It is the structure schematic drawing of spoiler in this embodiment 1.

[0023] Fig. 3 It is the structure schematic drawing at pressurizing structure in this embodiment 1 and embodiment 2.

[0024] Fig. 4 It is the structure schematic drawing of nuclear power helium compressor isolation pressure maintaining overhauling device in this embodiment 2.

[0025] Fig. 5 It is the structure schematic drawing of spoiler in this embodiment 2.

[0026] Fig. 6 It is the structure schematic drawing of sliding block under the left sliding state in this embodiment 2.

[0027] Fig. 7 It is the structure schematic drawing of sliding block under the right sliding state in this embodiment 2.

[0028] In the figure: 1, pressure vessel cylinder; 2, jacket cylinder; 3, lifting drive device; 4, fixed seat; 5, helium compressor; 6, cooling water inlet; 7, cooling water outlet; 8, first impeller; 9, spoiler; 91, limit housing; 9101, air hole one; 9102, exhaust hole; 92, sliding block; 9201, air hole two; 93, reciprocating lead screw; 94, one-way air valve; 10, transmission shaft; 11, baffle; 12, guide plate. DETAILED DESCRIPTION

[0029] The technical solutions in the embodiments of the utility model will be clearly and completely described below with reference to the drawings in the embodiments of the utility model. Obviously, the described embodiments are only part of the embodiments of the utility model, rather than all the embodiments. Based on the embodiments in the utility model, all other embodiments obtained by those skilled in the art without creative labor fall within the scope of protection of the utility model.

[0030] Embodiment 1: refer to Figs. 1-3 The utility model discloses a nuclear power helium compressor isolation pressure maintaining overhauling device, including the pressure vessel cylinder 1 and the jacket cylinder 2 of inside and outside setting, the cooling channel is formed between the pressure vessel cylinder 1 and the jacket cylinder 2, the upper and lower ends of the jacket cylinder 2 are provided with cooling water outlet 7 and cooling water inlet 6 respectively, during the overhauling process, the pressure vessel cylinder 1 is cooled by the cooperation of cooling water inlet 6, cooling channel, cooling water outlet 7 and the existing conventional refrigeration equipment and circulating equipment outside.

[0031] Among them, the inner bottom end of pressure vessel cylinder 1 is installed with lifting drive device 3, the top output end of lifting drive device 3 is installed with fixed seat 4, and helium compressor 5 is placed and fixed on the upper end of fixed seat 4, and the lifting drive device 3 can realize the lifting of helium compressor 5 in the mode of motor drive cooperating with spiral lifting structure.

[0032] Pressure vessel cylinder 1 is uniformly distributed with spoiler structure, and the spoiler structure includes first impeller 8, spoiler 9 and transmission shaft 10, wherein transmission shaft 10 penetrates pressure vessel cylinder 1 and is sealingly and rotatably installed on pressure vessel cylinder 1, first impeller 8 is located between pressure vessel cylinder 1 and jacket cylinder 2 and is fixed to one end of transmission shaft 10, and spoiler 9 is installed on the end of transmission shaft 10 located inside pressure vessel cylinder 1.

[0033] Specifically, spoiler 9 is a second impeller.

[0034] Based on the matching arrangement of the above structure, the cooling water in the cooling channel impacts the first impeller 8 from bottom to top in the circulation process to make the first impeller 8 rotate, and the first impeller 8 drives the turbulence member 9 to disturb the high-temperature gas pressure inside the pressure container cylinder 1 through the transmission shaft 10, so that the high-temperature gas pressure inside the pressure container cylinder 1 is uniformly cooled.

[0035] In order to ensure that the impact force of the water flow on the first impeller 8 can make the first impeller 8 rotate, a plurality of partitions 11 are fixed between the pressure container cylinder 1 and the jacket cylinder 2, the turbulence structure is located between two adjacent partitions 11, and a guide plate 12 is fixed to one side end of the partition 11, and the end of the guide plate 12 away from the partition 11 is inclined upward.

[0036] Embodiment 2: Reference Figs. 4-7 The nuclear power helium gas compressor isolation pressure maintaining overhauling device shown in the figure is different from embodiment 1 in that the turbulence member 9 comprises a limiting shell 91, a sliding block 92 and a reciprocating lead screw 93.

[0037] Specifically, the limiting shell 91 is fixed to the inner wall of the pressure container cylinder 1, the transmission shaft 10 is coaxially fixed to the reciprocating lead screw 93 at the end inside the pressure container cylinder 1, the sliding block 92 is slidingly installed inside the limiting shell 91, and a reciprocating shaft sleeve matched with the reciprocating lead screw 93 is installed at the middle of the sliding block 92.

[0038] The end of the limiting shell 91 away from the pressure container cylinder 1 is provided with a gas hole one 9101, the end of the limiting shell 91 close to the pressure container cylinder 1 is provided with an exhaust hole 9102, the sliding block 92 is provided with a gas hole two 9201, and a one-way air valve 94 is installed in each of the gas hole one 9101 and the gas hole two 9201, the one-way air valve 94 in the gas hole one 9101 allows air to enter the inside of the limiting shell 91, and the one-way air valve 94 in the gas hole two 9201 allows air to enter the side of the sliding block 92 close to the pressure container cylinder 1.

[0039] The first impeller 8 rotates with the transmission shaft 10 and the reciprocating lead screw 93, and the reciprocating lead screw 93 drives the sliding block 92 to reciprocate in the limiting shell 91 along the length direction, specifically, Fig. 6 and Fig. 7 As shown, in the process of the sliding block 92 sliding to the left, the high-temperature gas in the middle of the pressure container cylinder 1 enters the limiting shell 91 through the gas hole one 9101, and at the same time, the high-temperature gas on the left side of the sliding block 92 is extruded by the sliding block 92 and is discharged outward from the exhaust hole 9102 to the inner wall of the pressure container cylinder 1 to be cooled; in the process of the sliding block 92 sliding to the right, the high-temperature gas on the right side of the sliding block 92 enters the left side of the sliding block 92 through the gas hole two 9201, and the above actions are repeated to continuously guide the high-temperature gas in the middle of the pressure container cylinder 1 to the inner wall of the pressure container cylinder 1 to be cooled, thereby enhancing the cooling effect on the helium gas compressor 5.

[0040] It should be further explained that the specific structure of the spoiler 9 is made of high-temperature-resistant material and will not be deformed by the high temperature in the pressure vessel cylinder 1. In addition, the nuclear power helium compressor isolation pressure maintaining overhauling device only limits its own cooling structure and function, and other existing technologies such as overhauling isolation valve, reactor primary loop, vacuum extraction channel and electric appliance penetrating channel are not repeated in the text and schematic diagram.

[0041] Finally, it should be pointed out that the above description is only the preferred embodiment of the present application and is not intended to limit the present application. Although the present application has been described in detail with reference to the foregoing embodiments, those skilled in the art can still modify the technical solutions recorded in the foregoing embodiments or make equivalent substitutions for some of the technical features, and any modification, equivalent substitution, improvement, etc. made within the spirit and principles of the present application shall be included in the protection scope of the present application.

Claims

1. A nuclear power helium compressor isolation pressure maintaining overhauling device, comprising an inner and outer pressure vessel cylinder (1) and a jacket cylinder (2), a cooling channel is formed between the pressure vessel cylinder (1) and the jacket cylinder (2), and a cooling water outlet (7) and a cooling water inlet (6) are arranged at the upper and lower ends of the jacket cylinder (2) respectively, characterized in that: the pressure vessel cylinder (1) is uniformly distributed with a turbulence structure, the turbulence structure comprises a first impeller (8), a turbulence member (9) and a transmission shaft (10); the transmission shaft (10) penetrates through the pressure vessel cylinder (1) and is sealingly and rotatably mounted on the pressure vessel cylinder (1), the first impeller (8) is located between the pressure vessel cylinder (1) and the jacket cylinder (2) and is fixed to one end of the transmission shaft (10), and the turbulence member (9) is mounted on the end of the transmission shaft (10) located inside the pressure vessel cylinder (1); the cooling water in the cooling channel impacts the first impeller (8) during circulation from bottom to top to make the first impeller (8) rotate, and the first impeller (8) drives the turbulence member (9) to disturb the high-temperature gas pressure inside the pressure vessel cylinder (1) through the transmission shaft (10) to make the high-temperature gas pressure inside the pressure vessel cylinder (1) receive uniform cooling. The turbulence member (9) is a second impeller. The turbulence member (9) comprises a limiting shell (91), a sliding block (92) and a reciprocating lead screw (93); the limiting shell (91) is fixed to the inner wall of the pressure vessel cylinder (1), the end of the transmission shaft (10) located inside the pressure vessel cylinder (1) is coaxially fixed with the reciprocating lead screw (93), the sliding block (92) is slidingly mounted inside the limiting shell (91), and the middle part of the sliding block (92) is provided with a reciprocating shaft sleeve matched with the reciprocating lead screw (93); 2. The device for isolating and maintaining pressure of a nuclear power helium gas compressor for repair according to claim 1, characterized in that: an air hole one (9101) is arranged at the end of the limiting shell (91) away from the pressure vessel cylinder (1), an air exhaust hole (9102) is arranged at the end of the limiting shell (91) close to the pressure vessel cylinder (1), an air hole two (9201) is arranged on the sliding block (92), and a one-way air valve (94) is arranged in each of the air hole two (9201) and the air hole one (9101), the one-way air valve (94) in the air hole one (9101) allows air to enter the inside of the limiting shell (91), and the one-way air valve (94) in the air hole two (9201) allows air to enter the side of the sliding block (92) close to the pressure vessel cylinder (1).

3. The device for isolating and maintaining pressure of a nuclear power helium gas compressor for repair according to claim 1, characterized in that: A plurality of partition plates (11) are fixed between the pressure vessel cylinder (1) and the jacket cylinder (2), and the turbulence structure is located between two adjacent partition plates (11). A guide plate (12) is fixed to one side end of the partition plate (11), and the end of the guide plate (12) away from the partition plate (11) is obliquely upwardly inclined. ​ 4. The device for isolating and maintaining pressure of a helium compressor of a nuclear power plant for repair according to claim 2 or 3, characterized in that: ​ 5. The device for isolating and maintaining pressure of a helium compressor of a nuclear power plant for repair according to claim 4, characterized in that: ​ 6. The device for isolating and maintaining pressure of a nuclear power helium gas compressor for repair according to claim 5, characterized in that: The inner bottom end of the pressure container cylinder (1) is provided with a lifting driving device (3), the top output end of the lifting driving device (3) is provided with a fixed seat (4), and the upper end of the fixed seat (4) is placed and fixed with a helium compressor (5).

Citation Information

Patent Citations

  • Isolation pressure-maintaining maintenance device for helium compressor of high-temperature gas cooled reactor

    CN212338148U