Nuclear power plant pressurizer surge nozzle insulation sleeve structure and system

Abstract

The present application relates to a kind of nuclear power plant surge line nozzle heat shield sleeve structure and system, comprising: support ring, fluid distribution cover, heat shield sleeve, nuclear power plant surge line nozzle and cladding layer.The nuclear power plant surge line nozzle heat shield sleeve structure and system described above when actually used, through the one end of support ring and the cladding layer of surge line nozzle connection, the other end and fluid distribution cover connection, the one end of heat shield sleeve is inserted into support ring and is connected with support ring, to form gap between the other end of heat shield sleeve and the safety end of surge line nozzle, radioactive particles generated in the annular space between heat shield sleeve and surge line nozzle during reactor operation can be discharged from the gap, thereby avoiding the difficulty and cost of in-service inspection caused by the fact that the safety end of heat shield sleeve surge line nozzle forms a sealed space, so that the risk of high radiation faced by inspection and maintenance personnel is reduced.

Description

Technical Field

[0001] This invention relates to the field of pressurizer equipment in nuclear power plants, and specifically to a heat insulation sleeve structure and system for the fluctuating nozzle of a nuclear power plant pressurizer. Background Technology

[0002] A known voltage regulator uses a thermal shock protection structure. The regulator's fluctuating nozzle consists of a fluctuating nozzle body, a fluctuating nozzle safety end, and a thermal shock protection insulation sleeve. The thermal shock protection insulation sleeve is an integral cylindrical body, with its lower end connected to the fluctuating nozzle safety end via a butt weld. An annular space is formed between the outer wall of the thermal shock protection insulation sleeve and the inner wall of the fluctuating nozzle body and the inner wall of the fluctuating nozzle safety end. Multiple small holes are formed on the upper wall of the thermal shock protection insulation sleeve near the fluctuating nozzle safety end. These holes allow the primary coolant to communicate with the annular space formed between the thermal shock protection insulation sleeve, the fluctuating nozzle body, and the fluctuating nozzle safety end. This allows the low-temperature coolant flowing into the fluctuating nozzle to enter the annular space through these holes, mix with the fluid inside the voltage regulator, and prevent the thermal shock protection insulation sleeve from being subjected to a large pressure difference between its inner and outer walls.

[0003] However, radioactive particles generated during the operation of the aforementioned structure tend to accumulate in the annular space. Because the lower end of the thermal shock insulation sleeve in the thermal shock protection structure used in nuclear power plant pressurizers is welded to the safety end of the surge nozzle to seal the annular space, it is difficult for radioactive particles to escape, making it inconvenient to inspect and maintain the bottom of the pressurizer during its service life. Summary of the Invention

[0004] Based on this, it is necessary to address the problem that the thermal shock protection structure used in existing nuclear power plant pressurizers has a closed annular space formed by the welding connection between the lower end of the thermal shock protection insulation sleeve and the safety end of the wave nozzle, which makes it difficult for radioactive particles to escape and makes it inconvenient to inspect and maintain the bottom of the pressurizer during service. Therefore, it is necessary to provide a thermal shock protection sleeve structure and system for the wave nozzle of a nuclear power plant pressurizer.

[0005] One embodiment of this application provides a heat insulation sleeve structure for the surge nozzle of a nuclear power plant pressurizer, comprising:

[0006] A support ring, one end of which is connected to the weld overlay of the voltage regulator's fluctuating nozzle;

[0007] A fluid distribution hood, the opening of which faces downwards, and the open end of which is connected to the end of the support ring away from the voltage regulator's fluctuating nozzle;

[0008] A heat insulation sleeve is located inside the voltage regulator's fluctuating nozzle. One end of the heat insulation sleeve extends into the support ring and is connected to the support ring. A gap is formed between the other end of the heat insulation sleeve and the safety end of the voltage regulator's fluctuating nozzle.

[0009] In actual use, the aforementioned heat insulation sleeve structure for the pressurizer fluctuating nozzle of a nuclear power plant connects one end of a support ring to the weld overlay of the pressurizer fluctuating nozzle and the other end to the opening of the fluid distribution shroud. One end of the heat insulation sleeve extends into and connects to the support ring, thus creating a gap between the other end of the heat insulation sleeve and the safe end of the pressurizer fluctuating nozzle. During reactor operation, radioactive particles generated in the annular space between the heat insulation sleeve and the pressurizer fluctuating nozzle can be discharged through the gap. This avoids the problem of radioactive particles being unable to be discharged due to the sealed space formed between the heat insulation sleeve and the safe end of the pressurizer fluctuating nozzle in the prior art. This reduces the difficulty and cost of in-service inspections and lowers the risk of high radiation exposure for inspection and maintenance personnel.

[0010] In one embodiment, the support ring includes an annular support portion and an annular connecting portion;

[0011] One axial end of the annular support is connected to the opening end of the fluid distribution hood, and the other axial end of the annular support is connected to the weld overlay layer.

[0012] The outer ring of the annular connecting part is connected to the inner wall of the annular support part, and the inner ring of the annular connecting part is connected to the end of the heat insulation sleeve away from the safety end;

[0013] The annular connecting part has multiple vent holes along its circumference.

[0014] In one embodiment, the annular support portion has multiple drain holes circumferentially arranged at one end near the voltage regulator's fluctuating nozzle.

[0015] In one embodiment, the inner annular surface of the end of the annular support where the drain hole is located forms an acute angle with the weld overlay layer.

[0016] In one embodiment, the fluid distribution cover has multiple vent holes.

[0017] In one embodiment, the outer wall of the heat insulation sleeve is provided with a plurality of protrusions along the circumference.

[0018] In one embodiment, the end face of the heat insulation sleeve near the safety end is provided with a plurality of grooves along the circumference of the heat insulation sleeve.

[0019] In one embodiment, the outer wall of the heat insulation sleeve is provided with a plurality of reference holes along the circumferential direction.

[0020] One embodiment of this application provides a thermal insulation sleeve system for a nuclear power plant pressurizer fluctuating nozzle. The nuclear power plant pressurizer fluctuating nozzle system includes a nuclear power plant pressurizer fluctuating nozzle, a weld overlay layer, and a thermal insulation sleeve structure for the nuclear power plant pressurizer fluctuating nozzle.

[0021] In actual use, the aforementioned nuclear power plant pressurizer fluctuating nozzle insulation sleeve system connects one end of a support ring to the weld overlay of the pressurizer fluctuating nozzle and the other end to the opening of the fluid distribution shroud. One end of the insulation sleeve extends into and connects to the support ring, allowing a gap to be formed between the other end of the insulation sleeve and the safe end of the pressurizer fluctuating nozzle. During reactor operation, radioactive particles generated in the annular space between the insulation sleeve and the pressurizer fluctuating nozzle can be discharged through the gap. This avoids the problem of radioactive particles being unable to be discharged due to the sealed space formed between the insulation sleeve and the safe end of the pressurizer fluctuating nozzle in the prior art. This reduces the difficulty and cost of in-service inspections and lowers the risk of high radiation exposure for inspection and maintenance personnel.

[0022] In one embodiment, the safety end has a protrusion that extends radially inward along the heat insulation sleeve, and the gap is formed between the protrusion and the end of the heat insulation sleeve opposite to the support ring.

[0023] In one embodiment, the inner wall of the protrusion is an arc-shaped concave surface. Attached Figure Description

[0024] Figure 1 A schematic diagram of the heat insulation sleeve structure of the surge nozzle of a nuclear power plant pressurizer according to one embodiment;

[0025] Figure 2 for Figure 1 A schematic diagram of the gap between the thermal insulation sleeve and the pressure vessel nozzle of the nuclear power plant pressurizer;

[0026] Figure 3 for Figure 1 Enlarged view of the middle support ring;

[0027] Figure 4 This is a schematic diagram of a support ring according to one embodiment.

[0028] Icon labels:

[0029] 100-Insulation sleeve structure for the surge nozzle of a nuclear power plant pressurizer;

[0030] 110-Support ring; 111-Annular support part; 112-Annular connecting part; 113-Vent hole; 114-Drain hole; 115-Outer ring; 116-Inner ring;

[0031] 120 - Fluid distribution hood; 121 - Vent hole;

[0032] 130 - Thermal insulation sleeve; 131 - Boss; 132 - Groove; 133 - Reference hole;

[0033] 140-gap;

[0034] 210 - Voltage regulator fluctuating nozzle; 211 - Weld overlay;

[0035] 220 - Safety end; 221 - Protrusion; 222 - Arc-shaped concave surface. Detailed Implementation

[0036] To make the above-mentioned objects, features, and advantages of the present invention more apparent and understandable, specific embodiments of the present invention will be described in detail below with reference to the accompanying drawings. Many specific details are set forth in the following description to provide a thorough understanding of the present invention. However, the present invention can be practiced in many other ways different from those described herein, and those skilled in the art can make similar modifications without departing from the spirit of the present invention. Therefore, the present invention is not limited to the specific embodiments disclosed below.

[0037] In the description of this invention, it should 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," and "circumferential" indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings. They are used only for the convenience of describing this invention and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation. Therefore, they should not be construed as limitations on this invention.

[0038] Furthermore, the terms "first" and "second" are used for descriptive purposes only and should not be construed as indicating or implying relative importance or implicitly specifying the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one of that feature. In the description of this invention, "a plurality of" means at least two, such as two, three, etc., unless otherwise explicitly specified.

[0039] In this invention, unless otherwise explicitly specified and limited, the terms "installation," "connection," "linking," and "fixing," etc., should be interpreted broadly. For example, they can refer to a fixed connection, a detachable connection, or an integral part; they can refer to a mechanical connection or an electrical connection; they can refer to a direct connection or an indirect connection through an intermediate medium; they can refer to the internal communication of two components or the interaction between two components, unless otherwise explicitly limited. Those skilled in the art can understand the specific meaning of the above terms in this invention according to the specific circumstances.

[0040] In this invention, unless otherwise explicitly specified and limited, "above" or "below" the second feature can mean that the first feature is in direct contact with the second feature, or that the first feature is in indirect contact with the second feature through an intermediate medium. Furthermore, "above," "over," and "on top" of the second feature can mean that the first feature is directly above or diagonally above the second feature, or simply that the first feature is at a higher horizontal level than the second feature. "Below," "below," and "under" the second feature can mean that the first feature is directly below or diagonally below the second feature, or simply that the first feature is at a lower horizontal level than the second feature.

[0041] It should be noted that when an element is referred to as being "fixed to" or "set on" another element, it can be directly on the other element or there may be an intervening element. When an element is considered to be "connected to" another element, it can be directly connected to the other element or there may be an intervening element. The terms "vertical," "horizontal," "upper," "lower," "left," "right," and similar expressions used herein are for illustrative purposes only and do not represent the only possible implementation.

[0042] Please refer to Figure 1 and Figure 2 An embodiment of the present invention provides a heat insulation sleeve structure 100 for a nuclear power plant pressurizer fluctuating nozzle, comprising: a support ring 110, a fluid distribution shroud 120, and a heat insulation sleeve 130.

[0043] When the aforementioned heat insulation sleeve structure 100 of the nuclear power plant pressurizer fluctuating nozzle is installed at the inlet of the nuclear power plant pressurizer fluctuating nozzle 210, one end of the support ring 110 is connected to the weld overlay 211 of the pressurizer fluctuating nozzle 210. The heat insulation sleeve 130 is partially located inside the pressurizer fluctuating nozzle 210. One end of the heat insulation sleeve 130 extends into and connects to the support ring 110, while the other end of the heat insulation sleeve 130 forms a gap 140 with the safety end 220 of the pressurizer fluctuating nozzle 210. This allows the heat insulation sleeve 130 to be suspended and fixed relative to the safety end 220 of the pressurizer fluctuating nozzle 210 through its connection with the support ring 110, and the end of the heat insulation sleeve 130 away from the support ring 110 is connected to the pressurizer fluctuating nozzle 210. A gap 140 is formed between the safety ends 220 of 10. The opening of the fluid distribution cover 120 faces downward, and the opening end of the fluid distribution cover 120 is connected to the end of the support ring 110 away from the voltage regulator fluctuation nozzle 210. This allows the fluid distribution cover 120 to be indirectly connected to the voltage regulator fluctuation nozzle 210 by connecting it to the end of the support ring 110 away from the voltage regulator fluctuation nozzle 210. This prevents too much installation work from being done in the narrow part of the voltage regulator fluctuation nozzle 210 and avoids the problem of inconvenient installation.

[0044] In actual use, the aforementioned heat insulation sleeve structure 100 for the pressurizer fluctuating nozzle of a nuclear power plant connects one end of the support ring 110 to the weld overlay 211 of the pressurizer fluctuating nozzle 210 and the other end to the opening of the fluid distribution shroud 120. One end of the heat insulation sleeve 130 extends into and connects to the support ring 110, thereby forming a gap 140 between the other end of the heat insulation sleeve 130 and the safety end 220 of the pressurizer fluctuating nozzle 210. Radioactive particles generated in the annular space between the heat insulation sleeve 130 and the pressurizer fluctuating nozzle 210 during reactor operation can be discharged through the gap 140. This avoids the problem of radioactive particles being unable to be discharged due to welding between the heat insulation sleeve 130 and the safety end 220 of the pressurizer fluctuating nozzle 210, which would create a sealed space between the heat insulation sleeve 130 and the pressurizer fluctuating nozzle 210. This reduces the difficulty and cost of installation and in-service inspection, and reduces the risk of high radiation exposure for inspection and maintenance personnel.

[0045] Specifically, one end of the support ring 110 is welded and fixed to the weld overlay 211 of the pressurizer fluctuating nozzle 210, and the other end is welded and fixed to the opening of the fluid distribution shroud 120. One end of the heat insulation sleeve 130 extends into the support ring 110 and is welded and fixed to the support ring 110. This reduces the risk of foreign objects falling into the nuclear power plant pressurizer fluctuating nozzle 210 due to excessive connecting parts.

[0046] Specifically, the fluid distribution cover 120 is a hemispherical shell made of sheet metal, which can prevent impurities from entering the coolant system and improve the mixing of fluctuating water and fluid in the pressure regulator.

[0047] Preferably, a gap 140 of 1.5-4 mm is formed between the heat insulation sleeve 130 and the safety end 220 of the voltage regulator fluctuating nozzle 210.

[0048] In one embodiment, the support ring 110 includes an annular support portion 111 and an annular connecting portion 112. One axial end of the annular support portion 111 is connected to the open end of the fluid distribution cover 120, and the other axial end of the annular support portion 111 is connected to the weld overlay layer 211. The outer ring 115 of the annular connecting portion 112 is connected to the inner wall of the annular support portion 111, and the inner ring 116 of the annular connecting portion 112 is connected to the end of the heat insulation sleeve 130 away from the safety end 220. This allows the end of the heat insulation sleeve 130 away from the safety end 220 to be connected to the annular support portion 111 through the annular connecting portion 112 with the inner ring 116 and the outer ring 115. This makes it easier for the heat insulation sleeve 130 to be connected to the support ring 110 after the end of the heat insulation sleeve 130 away from the safety end 220 extends into the support ring 110. The annular connection 112 has multiple vent holes 113 circumferentially open, so that the upper end of the annular space between the heat insulation sleeve 130 and the pressurizer fluctuating nozzle 210 is open. This ensures that the fluid velocity in the annular space between the heat insulation sleeve 130 and the pressurizer fluctuating nozzle 210 is not too fast. The fluid mainly transfers heat through natural convection, which has a large thermal resistance and can play a good role in heat insulation and thermal shock prevention. This prevents the pressurizer fluctuating nozzle 210, the safety end 220 of the pressurizer fluctuating nozzle 210, and the weld of the isolation layer between the pressurizer fluctuating nozzle 210 and the safety end 220 from thermal fatigue damage or thermal shock. At the same time, it ensures the flowability of fluid in the gap space, so that radioactive particles generated in the annular space between the heat insulation sleeve 130 and the pressurizer fluctuating nozzle 210 during reactor operation can be discharged from the gap 140.

[0049] Preferably, the annular connecting part 112 has 2-4 vent holes 113 with a diameter of 6-10mm along the circumference. The angle between the axis of the vent hole 113 and the central axis of the voltage regulator fluctuating nozzle 210 is 0-60°, so that the fluid can pass through the vent hole 113 more smoothly.

[0050] In one embodiment, the side of the annular connecting portion 112 facing the fluid distribution cover 120 is a convex surface, and the side of the annular connecting portion 112 facing the weld overlay layer 211 is a concave surface, thereby forming an arc-shaped rounded corner of the annular connecting portion 112, which makes the flow field more uniform and the stress on the support ring 110 lower.

[0051] Preferably, the support ring 110 is an integral forging, thereby making the connection between the annular connecting part 112 and the annular support part 111 more secure.

[0052] Preferably, the end of the annular connecting portion 112 near the safety end 220 of the voltage regulator fluctuating nozzle 210 is an inner ring 116, and the end near the fluid distribution cover 120 is an outer ring 115, so that the opening of the annular groove formed by the annular connecting portion 112 and the annular support portion 111 faces the gap 140, thereby preventing radioactive particles from accumulating in the annular groove formed by the annular connecting portion 112 and the annular support portion 111.

[0053] In another embodiment, the distance between the inner ring 116 of the annular connection 112 and the safety end 220 of the voltage regulator fluctuating nozzle 210 is equal to the distance between the outer ring 115 of the annular connection 112 and the safety end 220 of the voltage regulator fluctuating nozzle 210.

[0054] In one embodiment, the annular support 111 has a plurality of drain holes 114 circumferentially opened at one end near the pressurizer fluctuating nozzle 210, so that radioactive particles generated in the annular space between the heat insulation sleeve 130 and the pressurizer fluctuating nozzle 210 during reactor operation can be discharged from the gap 140.

[0055] Preferably, the annular support 111 has an arc-shaped groove at one end near the weld overlay 211, and forms a semi-circular drain hole 114 with the weld overlay 211.

[0056] Preferably, the annular support 111 has 5-8 drain holes 114 evenly distributed circumferentially at one end near the voltage regulator fluctuating nozzle 210, and the diameter of the drain holes 114 is 10.5-14.5 mm.

[0057] In one embodiment, the inner ring 116 surface of the end of the annular support 111 with the drain hole 114 forms an acute angle with the weld overlay 211, thereby making the welding operation more convenient and more stable, allowing radioactive particles to be discharged smoothly and avoiding the deposition of radioactivity.

[0058] Preferably, the inner ring 116 surface of the end of the annular support 111 with the drain hole 114 forms an angle of 75-90° with the weld overlay layer 211.

[0059] In one embodiment, the fluid distribution hood 120 is provided with a plurality of vent holes 121, thereby enabling fluid distribution and allowing better natural convection to form inside the heat insulation sleeve structure 100 of the pressurizer fluctuating nozzle. The fluid enters the exhaust port 113 through the vent holes 121 and then flows out through the gap 140 formed between the heat insulation sleeve 130 and the safety end 220 of the pressurizer fluctuating nozzle 210, thereby allowing the radioactive particles formed between the heat insulation sleeve 130 and the pressurizer fluctuating nozzle 210 to flow out with the fluid.

[0060] Preferably, the number of vent holes 121 is 1500-2000, the diameter of the vent holes 121 is 9-10.5mm, and the distance between the vent holes 121 is 2.0-7.0mm, so that the fluid distribution is more uniform and foreign objects are prevented from entering the voltage regulator's fluctuating nozzle 210.

[0061] In one embodiment, the outer wall of the heat insulation sleeve 130 is provided with a plurality of protrusions 131 along the circumferential direction, so that the protrusions 131 can play a certain supporting role between the heat insulation sleeve 130 and the voltage regulator fluctuating nozzle 210, preventing the heat insulation sleeve 130, which is only connected to the support ring 110 at one end, from forming a cantilever beam structure and causing the heat insulation sleeve 130 to vibrate and collide with the voltage regulator fluctuating nozzle 210 when fluid flows in or out of the fluctuating nozzle.

[0062] Specifically, the boss 131 and the outer wall of the heat insulation sleeve 130 are fitted with a clearance, thereby avoiding damage caused by the collision between the inside of the heat insulation sleeve 130 and the boss 131 when the heat insulation sleeve 130 is inserted into the voltage regulator's fluctuating nozzle 210.

[0063] Preferably, the radial gap between the boss 131 and the outer wall of the heat insulation sleeve 130 is 0.5-0.7 mm.

[0064] In one embodiment, the end face of the heat insulation sleeve 130 near the safety end 220 is provided with a plurality of grooves 132 along the circumference of the heat insulation sleeve 130, thereby increasing the area of ​​the gap 140 between the heat insulation sleeve 130 and the safety end 220, thereby greatly reducing the accumulation of radioactive particles between the heat insulation sleeve 130 and the safety end 220. At the same time, there is still a gap 140 between the part of the heat insulation sleeve 130 without grooves 132 and the safety end 220, so that the fluid flow rate is not too fast. The fluid mainly transfers heat by natural convection, which has a large thermal resistance and can play a good role in heat insulation and thermal shock prevention. This protects the voltage regulator fluctuating nozzle 210, the safety end 220 of the voltage regulator fluctuating nozzle 210, and the weld between the voltage regulator fluctuating nozzle 210 and the safety end 220 from thermal fatigue damage or thermal shock.

[0065] Specifically, the groove 132 is semi-circular, the number of grooves 132 is 8-20, and the diameter of the groove 132 is 3-8mm.

[0066] In one embodiment, the outer wall of the heat insulation sleeve 130 is provided with a plurality of reference holes 133 along the circumferential direction, so that the position of the reference holes 133 can provide a reference for non-destructive testing of the weld to check whether the heat insulation sleeve 130 has fallen off or deformed.

[0067] Preferably, the diameter of the reference hole 133 is 6-16mm, and the total radial cross-sectional area of ​​the multiple reference holes 133 is less than 30% of the radial cross-sectional area of ​​the annular gap between the heat insulation sleeve 130 and the voltage regulator fluctuating nozzle 210, thereby making the fluid flow more uniform and the flow field more gentle, thus reducing the impact on the heat insulation sleeve 130.

[0068] One embodiment of this application provides a nuclear power plant pressurizer flue nozzle insulation sleeve 130 system. The nuclear power plant pressurizer flue system includes a nuclear power plant pressurizer flue nozzle 210, a weld overlay layer 211, and a nuclear power plant pressurizer flue nozzle insulation sleeve structure 100.

[0069] In actual use, the aforementioned nuclear power plant pressurizer fluctuating nozzle insulation sleeve 130 system, through the connection of one end of the support ring 110 to the weld overlay layer 211 of the pressurizer fluctuating nozzle 210 and the other end to the opening of the fluid distribution shroud 120, allows one end of the insulation sleeve 130 to extend into and connect to the support ring 110. This creates a gap 140 between the other end of the insulation sleeve 130 and the safety end 220 of the pressurizer fluctuating nozzle 210. Radioactive particles generated in the annular space between the insulation sleeve 130 and the pressurizer fluctuating nozzle 210 during reactor operation can be discharged through the gap 140. This avoids the formation of a sealed space between the insulation sleeve 130 and the safety end 220 of the pressurizer fluctuating nozzle 210, which would otherwise prevent radioactive particles from being discharged. This reduces the difficulty and cost of in-service inspections and lowers the risk of high radiation exposure for inspection and maintenance personnel.

[0070] In one embodiment, the safety end 220 has a protrusion 221 that protrudes radially inward along the heat insulation sleeve 130, thereby forming a gap 140 between the protrusion 221 and the end of the heat insulation sleeve 130 away from the support ring 110, so that radioactive particles generated in the annular space between the heat insulation sleeve 130 and the pressurizer fluctuating nozzle 210 during reactor operation can be discharged from the gap 140.

[0071] In one embodiment, the inner wall of the protrusion 221 is an arc-shaped concave surface 222, which makes the fluid flow more smooth and avoids the accumulation of radioactive particles caused by poor fluid flow at right-angle corners, so that radioactive particles can be discharged smoothly.

[0072] The technical features of the above embodiments can be combined in any way. For the sake of brevity, not all possible combinations of the technical features in the above embodiments are described. However, as long as there is no contradiction in the combination of these technical features, they should be considered to be within the scope of this specification.

[0073] The embodiments described above are merely illustrative of several implementations of the present invention, and while the descriptions are relatively specific and detailed, they should not be construed as limiting the scope of the invention patent. It should be noted that those skilled in the art can make various modifications and improvements without departing from the concept of the present invention, and these all fall within the protection scope of the present invention. Therefore, the protection scope of this invention patent should be determined by the appended claims.

Claims

1. A heat insulation sleeve structure for the surge nozzle of a nuclear power plant pressurizer, characterized in that, include: The support ring includes an annular support portion and an annular connecting portion. One axial end of the annular support portion is connected to the opening end of the fluid distribution hood, and the other axial end of the annular support portion is connected to the weld overlay layer. The outer ring of the annular connecting portion is connected to the inner wall of the annular support portion, and the inner ring of the annular connecting portion is connected to the end of the heat insulation sleeve away from the safety end. The annular support portion near the end of the voltage regulator's fluctuating nozzle has multiple drain holes along the circumference, and the annular connecting portion has multiple vent holes along the circumference. A fluid distribution hood, the opening of which faces downwards, and the open end of which is connected to the end of the support ring away from the voltage regulator's fluctuating nozzle; A heat insulation sleeve is located inside the voltage regulator's fluctuating nozzle. One end of the heat insulation sleeve extends into the support ring and is connected to the support ring. A gap is formed between the other end of the heat insulation sleeve and the safety end of the voltage regulator's fluctuating nozzle.

2. The thermal insulation sleeve structure for the pressurizer fluctuating nozzle of a nuclear power plant according to claim 1, characterized in that, The angle between the axis of the exhaust port and the central axis of the voltage regulator's fluctuating nozzle is 0-60°.

3. The thermal insulation sleeve structure for the pressurizer fluctuating nozzle of a nuclear power plant according to claim 1, characterized in that, The side of the annular connecting part facing the fluid distribution cover is a convex surface, and the side of the annular connecting part facing the weld overlay layer is a concave surface.

4. The thermal insulation sleeve structure for the pressurizer fluctuating nozzle of a nuclear power plant according to claim 1, characterized in that, The inner annular surface of the end of the annular support where the drain hole is located forms an acute angle with the weld overlay layer.

5. The thermal insulation sleeve structure for the pressurizer fluctuating nozzle of a nuclear power plant according to claim 1, characterized in that, The fluid distribution cover has multiple vent holes.

6. The thermal insulation sleeve structure for the pressurizer fluctuating nozzle of a nuclear power plant according to claim 5, characterized in that, The outer wall of the heat insulation sleeve is provided with multiple protrusions along the circumference.

7. The thermal insulation sleeve structure for the pressurizer fluctuating nozzle of a nuclear power plant according to claim 1, characterized in that, The end face of the heat insulation sleeve near the safety end has multiple grooves along its circumference.

8. The thermal insulation sleeve structure for the pressurizer fluctuating nozzle of a nuclear power plant according to claim 1, characterized in that, The outer wall of the heat insulation sleeve is provided with multiple reference holes along the circumference.

9. A thermal insulation sleeve system for the pressurizer fluctuating nozzle of a nuclear power plant, characterized in that, The nuclear power plant pressurizer flue nozzle insulation sleeve system includes a nuclear power plant pressurizer flue nozzle, a weld overlay layer, and the nuclear power plant pressurizer flue nozzle insulation sleeve structure as described in any one of claims 1-8.

10. The nuclear power plant pressurizer fluctuating nozzle insulation sleeve system according to claim 9, characterized in that, The safety end has a protrusion that extends radially inward along the heat insulation sleeve, and the gap is formed between the protrusion and the end of the heat insulation sleeve opposite to the support ring.

11. The nuclear power plant pressurizer fluctuating nozzle insulation sleeve system according to claim 10, characterized in that, The inner wall of the protrusion is an arc-shaped concave surface.

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