Heating assembly and heating system for hydraulic pressure test of nuclear power station

Abstract

The utility model relates to the technical field of nuclear power stations, and provides a heating assembly and a heating system for a hydraulic test of a nuclear power station. The heating assembly comprises a flexible heating body, a protective layer and a heat preservation layer, wherein the protective layer and the heat preservation layer are arranged on the two opposite sides of the flexible heating body respectively. The heating system for the hydraulic pressure test of the nuclear power station comprises a nuclear reaction device and a heating assembly, and the heating assembly is configured to be attached to the outer surface of the nuclear reaction device. The heating assembly is directly attached to the metal outer surface of the nuclear reaction device, the metal is directly heated in a heat conduction mode and can be electrified at any time, and the heating period is effectively shortened; the flexible heating body can be tightly attached to the outer surface of the nuclear reaction device, so that the contact area can be increased, and the heat loss during heating can be reduced; the protective layer can improve the pulling resistance of the whole heating assembly and reduce contact abrasion; the heat preservation layer can reduce loss of heat generated by the flexible heating body to the air, and the heating efficiency is improved.

Description

Technical Field

[0001] The present application relates to the technical field of nuclear power plants, and in particular provides a heating component and a heating system for a water pressure test of a nuclear power plant. Background Art

[0002] During the hydraulic test of a pressurized water reactor nuclear power plant, according to the requirements of RSE-M (Rules and Specifications for In-Service Inspection of Mechanical Equipment of the Nuclear Island of a Pressurized Water Reactor Nuclear Power Plant, R: In-Service Inspection, S: Supervision, E: Testing, M: Maintenance), in order to avoid the risk of equipment damage caused by the increase of the brittle transition temperature, it is necessary to ensure that the metal temperature on the secondary side of the nuclear reactor is higher than the test temperature.

[0003] In existing testing technology, an external water circulation heating system is used to continuously circulate and inject high-temperature medium water into the secondary side of a nuclear reactor (steam generator, reactor pressure vessel, etc.), thereby heating the metal on the secondary side of the nuclear reactor. However, due to the thickness of the metal shell of the nuclear reactor, the heating rate is low, which restricts the overall heating efficiency of the secondary side of the nuclear reactor. In addition, the medium water needs to be heated in advance, and the heat can only be transferred to the metal by filling the heated water into a pipe and sending it to the inside of the equipment to be heated, resulting in a long heating time and low heating efficiency. In addition, during the water pressure test, the water circulation system cannot be used to heat the metal. If the test encounters unexpected obstacles and the test time exceeds expectations, the metal will slowly decrease in temperature without heating means during the test, which may lead to the risk of the metal temperature not meeting the requirements and causing the test to fail. Utility Model Content

[0004] The purpose of the embodiments of the present application is to provide a heating assembly and a heating system for a nuclear power plant water pressure test, aiming to solve the problem of low heating efficiency of the nuclear reactor device in the existing nuclear power plant heating system.

[0005] To achieve the above objectives, the technical solution adopted in this application is:

[0006] In a first aspect, an embodiment of the present application provides a heating component for heating a metal to be heated; the heating component includes a flexible heating element and a protective layer and an insulation layer respectively arranged on opposite sides of the flexible heating element; the protective layer is used to be attached to the outer surface of the metal to be heated.

[0007] The beneficial effects of the present application are as follows: the heating component includes a flexible heating element that can be tightly attached to the outer surface of the metal to be heated, which is beneficial to increase the contact area and reduce heat loss during heating; the protective layer can enhance the tensile strength of the entire heating component and reduce the contact wear between the protective layer and the outer surface of the metal, thereby improving structural stability; the thermal insulation layer can reduce the loss of heat generated by the flexible heating element into the air, thereby improving heating efficiency.

[0008] In a possible design, the heating assembly further includes a heat reflecting film, which is disposed between the flexible heating element and the thermal insulation layer.

[0009] By adopting the above technical solution, the heat-reflecting film is arranged on the side of the flexible heating element away from the metal outer surface of the nuclear reactor, and the flexible heating element is attached to the metal outer surface for direct heating. The heat-reflecting film can further reflect the heat generated by the flexible heating element to the side of the metal outer surface, thereby reducing the loss of heat into the air and effectively improving the heating efficiency.

[0010] In a possible design, the heating assembly further includes a magnetic element located within the protective layer.

[0011] By adopting the above technical solution, the flexible heating body can be closely fitted to the metal surface through the magnetic element, and the connection is firm.

[0012] In one possible design, the flexible heating body includes a heating plate and a wrapping layer respectively wrapped on opposite sides of the heating plate, and the protective layer is arranged on the wrapping layer on one side of the heating plate; the magnetic element is arranged on the heating plate and embedded in the wrapping layer and the protective layer in sequence.

[0013] By adopting the above technical solution, the magnetic element is arranged on the internal metal heating plate, and the structural design is stable.

[0014] In a possible design, a mounting hole for mounting the magnetic element is provided on the heating plate.

[0015] By adopting the above technical solution, a mounting hole for mounting the magnetic element is reserved on the heating plate, and the magnetic element can be directly mounted in the mounting hole, which is convenient and quick to install.

[0016] In a possible design, the heating plate is provided with staggered slot structures.

[0017] By adopting the above technical solution, the groove structure is distributed on the entire heating plate, which is conducive to the bending of the heating plate, so that the heating plate can be bent and attached to the outside of the steam generator or reactor pressure vessel; the heat conductivity is good, and the heating efficiency is effectively improved.

[0018] In a possible design, the heating component further includes a temperature sensor, which is disposed on any one of the heating plate, the wrapping layer, and the protective layer.

[0019] By adopting the above technical solution, the temperature sensor detects the temperature and sends a temperature signal; the remote control terminal is configured to control the heating power of the heating component according to the relationship between the temperature signal and the set temperature threshold.

[0020] In a possible design, the heating component further includes a connecting portion electrically connected to the silicone heating body, and the connecting portion is configured to be connected to an external power source.

[0021] In a second aspect, an embodiment of the present application provides a heating system for water pressure testing of a nuclear power plant, comprising a nuclear reactor and the heating component, wherein the protective layer of the heating component is configured to be adhered to the outer surface of the nuclear reactor; the nuclear reactor is in a steam generator and / or a reactor pressure vessel.

[0022] By adopting the above technical solution, the nuclear reactor device is heated by directly attaching the heating component to the metal outer surface of the nuclear reactor device; the metal is heated directly by heat conduction and can be powered on at any time, which effectively shortens the heating period and helps improve the efficiency of the water pressure test.

[0023] In one possible design, the nuclear power plant heating system further includes a remote control terminal communicatively connected to the heating component.

[0024] By adopting the above technical solution, the remote control terminal can control the power of the heating component in real time, which is beneficial to temperature control. BRIEF DESCRIPTION OF THE DRAWINGS

[0025] In order to more clearly illustrate the technical solutions in the embodiments of the present application, the following briefly introduces the drawings required for use in the embodiments or descriptions of the prior art. Obviously, the drawings described below are only some embodiments of the present application. For ordinary technicians in this field, other drawings can be obtained based on these drawings without any creative work.

[0026] Figure 1 A schematic structural diagram of a heating system for a nuclear power plant hydrostatic test according to an embodiment of the present application;

[0027] Figure 2 A schematic structural diagram of a steam generator provided in one embodiment of the present application;

[0028] Figure 3 A schematic diagram showing the result of attaching a heating assembly provided in one embodiment of the present application to the outer surface of a nuclear reactor device;

[0029] Figure 4 A schematic diagram of the three-dimensional structure of a heating assembly provided in one embodiment of the present application;

[0030] Figure 5A schematic cross-sectional view of a heating assembly according to an embodiment of the present application;

[0031] Figure 6 for Figure 5 An enlarged view of the local A in FIG;

[0032] Figure 7 This is a schematic diagram of the structure of a heating sheet provided in one embodiment of the present application, wherein the heating sheet is designed as a rectangular structure;

[0033] Figure 8 This is a schematic structural diagram of a heating plate provided in one embodiment of the present application, wherein the heating plate is designed as a fan-shaped structure.

[0034] Among them, the reference numerals in the figures are:

[0035] 1000. Nuclear reactor;

[0036] 100, reactor pressure vessel; 110, outer cylinder; 120, nozzle;

[0037] 200, steam generator; 201, first part; 202, steam generator secondary side;

[0038] 203, water inlet; 204, water outlet; 205, U-shaped heat transfer tube; 210, tube sheet;

[0039] 300, connecting part; 310, heating component; 320, remote control terminal;

[0040] 1. Flexible heating element; 11. Heating sheet; 12. Wrapping layer;

[0041] 2. Protective layer; 3. Insulation layer; 4. Heat reflective film;

[0042] 5. Magnetic element; 6. Mounting hole; 7. Slot structure. DETAILED DESCRIPTION

[0043] The following describes in detail embodiments of the present application, examples of which are shown in the accompanying drawings, wherein the same or similar reference numerals throughout represent the same or similar elements or elements having the same or similar functions. The embodiments described below with reference to the accompanying drawings are exemplary and are intended to be used to explain the present application, and should not be construed as limiting the present application.

[0044] In the description of this application, it should be understood that the terms "length", "width", "up", "down", "front", "back", "left", "right", "vertical", "horizontal", "top", "bottom", "inside", "outside", etc., indicating the orientation or position relationship, are based on the orientation or position relationship shown in the accompanying drawings, and are only for the convenience of describing this application and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and therefore cannot be understood as a limitation on this application.

[0045] 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 the technical features being referred to. Thus, a feature defined as "first" or "second" may explicitly or implicitly include one or more of the features. Throughout the description of this application, "plurality" means two or more, unless otherwise specifically defined.

[0046] In this application, unless otherwise expressly specified or limited, terms such as "mounted," "connected," "connect," and "fixed" should be understood in a broad sense. For example, they may refer to fixed connections, detachable connections, or integration; mechanical connections or electrical connections; direct connections or indirect connections through an intermediate medium; and internal connections between two components or interactions between two components. Those skilled in the art will understand the specific meanings of these terms in this application based on specific circumstances.

[0047] In this application, the terms "one embodiment", "some embodiments", "examples", "specific examples", or "some examples" mean that the specific features, structures, materials or characteristics described in conjunction with the embodiment or example are included in at least one embodiment or example of the present application. In this specification, the schematic representations of the above terms do not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described can be combined in any one or more embodiments or examples in a suitable manner. In addition, those skilled in the art can combine and combine different embodiments or examples described in this specification and the features of different embodiments or examples without contradiction.

[0048] In existing nuclear power plant hydraulic testing technology, an external water circulation heating system is usually used to continuously circulate and inject high-temperature medium water into the secondary side of the nuclear reactor (steam generator, reactor pressure vessel, etc.), thereby heating the metal on the secondary side of the nuclear reactor. However, due to the thickness of the metal shell of the nuclear reactor, the heating rate is low, which restricts the overall heating efficiency of the secondary side of the nuclear reactor. In addition, the medium water needs to be heated in advance, and the heat can only be transferred to the metal by filling the heated water into the pipe and sending it to the inside of the equipment to be heated, resulting in a long heating time and low heating efficiency. In addition, during the hydraulic test, the water circulation system cannot be used to heat the metal. If the test encounters unexpected obstacles and the test time exceeds expectations, the metal will slowly cool down without heating means during the test, which may lead to the risk of the metal temperature not meeting the requirements and causing the test to fail.

[0049] Based on this, in order to solve the above problems, the present application designs a heating component and a heating system for water pressure testing of nuclear power plants; the heating component includes a flexible heating element and a protective layer and a thermal insulation layer respectively arranged on opposite sides of the flexible heating element. The heating system for the water pressure test of a nuclear power plant includes a nuclear reactor and a heating component, and the heating component is configured to be attached to the outer surface of the nuclear reactor. By directly attaching the heating component to the metal outer surface of the nuclear reactor, the metal can be heated directly by heat conduction and can be powered on at any time, thereby effectively shortening the heating period; the flexible heating element can be tightly attached to the outer surface of the nuclear reactor, which is beneficial to increase the contact area and reduce heat loss during heating; the protective layer can enhance the pull-resistance of the entire heating component and reduce contact wear; the thermal insulation layer can reduce the loss of heat generated by the flexible heating element into the air, thereby improving the heating efficiency.

[0050] Please refer to Figure 1-Figure 3 An embodiment of the present application provides a heating system for a water pressure test of a nuclear power plant, including a nuclear reactor 1000 and a heating component 310; the heating component 310 is used to be attached to the metal outer surface of the nuclear reactor 1000.

[0051] In some embodiments, the heating element 310 includes a flexible heating element 1 and a protective layer 2 and a thermal insulation layer 3 respectively disposed on opposite sides of the flexible heating element 1 ; the protective layer 2 is used to be attached to the metal outer surface of the nuclear reactor 1000 .

[0052] Specifically, the flexible heating element 1 can generate heat to heat the metal outer surface of the nuclear reactor 1000 after being energized by an external power source. The flexible heating element 1 can be stretched and deformed to better wrap around the metal outer surface. The protective layer 2 is in contact with the metal outer surface of the nuclear reactor 1000. The protective layer 2 should have good flexibility and wear resistance, which can improve the tensile strength of the entire heating component 310, and reduce the contact wear between the protective layer 2 and the metal outer surface, thereby improving the structural stability of the heating component 310. The thermal insulation layer 3 is arranged on the side of the flexible heating element 1 away from the metal outer surface, which can reduce the loss of heat generated by the flexible heating element 1 into the air and improve the heating efficiency.

[0053] Hydrostatic testing is a crucial step in nuclear power plant equipment installation. It can be used to assess the strength and sealing performance of equipment. Nuclear reactor 1000 includes steam generator 200, and hydrostatic testing involves testing both the steam generator 200 and the primary circuit.

[0054] Steam generator 200 participates in both the primary and secondary circuits of the nuclear reactor. The primary circuit refers to the circuit where water directly exchanges heat with the nuclear reactor. Specifically, the nuclear reactor generates enormous amounts of heat energy due to nuclear fuel fission. Water pumped into the core by the main pump is heated to high temperature and high pressure. This high temperature and high pressure water flows through the heat transfer tubes within steam generator 200, transferring heat energy through the tube walls to the cooling water in the secondary circuit. After releasing heat, it is then pumped back to the nuclear reactor by the main pump for reheating. This continuous circulation of water within a closed circuit is called the primary circuit.

[0055] The secondary circuit is a circuit used to exchange heat with the high-temperature water in the primary circuit and generate steam. Figure 2Figure 2 shows a schematic diagram of the structure of a steam generator 200. The steam generator 200 includes a tube sheet 210, a first portion 201 participating in the primary circuit, and a second portion, or steam generator secondary side 202, participating in the secondary circuit heat exchange process and generating steam. The first portion 201 and the steam generator secondary side 202 are isolated from each other. Specifically, the first portion 201 includes a water inlet 203 for the high-temperature, high-pressure water in the primary circuit, a water outlet 204 for the water outflow, and U-shaped heat transfer tubes 205 for heat exchange with the cooling water in the secondary circuit. The high-temperature, high-pressure water in the primary circuit enters the U-shaped heat transfer tubes 205 in the steam generator 200 through the water inlet 203, then exchanges heat with the cooling water in the steam generator secondary side 202. After the heat exchange, the water temperature is reduced and the water flows out of the steam generator 200 through the water outlet 204, returning to the pressure vessel in the primary circuit. The tube sheet 210 is the boundary component in the steam generator 200 that separates the first portion 201 from the steam generator secondary side 202. That is, in the steam generator 200, one side of the tube sheet 210 is a chamber for holding high-temperature, high-pressure water in the primary circuit, through which the U-shaped heat transfer tubes 205 pass. The other side of the tube sheet 210 is a chamber for holding cooling water in the secondary circuit.

[0056] During the hydrostatic test, the shell temperature of the steam generator secondary side must be kept above the test temperature to reduce the risk of equipment damage caused by an increase in the brittle transition temperature. Therefore, the metal on the steam generator secondary side 202 must be heated. Since the tube sheet 210 is typically 500mm-700mm thick, making it an ultra-thick forging, it heats up slowly during heating. The heating rate of the tube sheet 210 limits the overall heating efficiency of the steam generator secondary side 202 metal.

[0057] Specifically, the heating assembly 310 is attached to the outer surface of the tube sheet 210 and directly heats the tube sheet 210. This allows the tube sheet 210 to be heated at any time without being constrained by the equipment recovery window at the test boundary, effectively shortening the heating period.

[0058] In some embodiments, reference Figure 1 The nuclear reactor 1000 further includes a reactor pressure vessel 100, which includes an outer cylinder 110 and a nozzle 120 disposed on the outer cylinder 110. The heating assembly 310 is further configured to adhere to the bottom of the outer cylinder 110 and the outer surface of the nozzle 120.

[0059] Specifically, the reactor pressure vessel 100 refers to the pressure vessel that houses the nuclear reactor. The reactor pressure vessel 100 includes an outer cylinder 110 and nozzles 120 disposed on the outer cylinder 110. The nozzles 120 are the water inlet and outlet of the reactor pressure vessel 100. The outer cylinder 110 is the main body of the reactor pressure vessel 100. During the hydrostatic test of the primary circuit of a pressurized water reactor nuclear power plant, the temperature of the bottom of the outer cylinder 110 and the nozzles 120 must be higher than the test temperature. Therefore, the heating assembly 310 is also disposed at the bottom of the outer cylinder 110 and the outer surface of the nozzles 120, allowing the heating assembly 310 to directly heat the bottom of the outer cylinder 110 and the nozzles 120. Directly heating the bottom of the outer cylinder 110 and the nozzles 120 by heat conduction improves heating efficiency, thereby improving the efficiency of the hydrostatic test. Furthermore, in related art, during a primary circuit hydrostatic test, if the test pressure exceeds 154 bar, the primary circuit's main pump cannot be activated for internal heating, potentially causing the test to fail due to insufficient metal temperature. However, the heating assembly 310 of the present application can heat the bottom of the outer cylinder 110 and the nozzle 120 at any time, unaffected by the hydrostatic test. This reduces the probability of test failure and further improves the efficiency of the hydrostatic test.

[0060] Multiple heating assemblies 310 are provided, and are disposed on the tube sheet 210, the bottom of the outer cylinder 110, and the outer surface of the nozzle 120, respectively. This allows simultaneous heating of all three locations, thereby improving heating efficiency. It is understood that multiple heating assemblies 310 may be provided at each location, for example, two heating assemblies may be provided on the outer surface of the tube sheet 210, two heating assemblies may be provided on the outer surface of the bottom of the outer cylinder 110, and two heating assemblies may be provided on the outer surface of the nozzle 120. This further improves heating efficiency and, in turn, the efficiency of the hydrostatic test.

[0061] The heating component of the present application and the heating system for the water pressure test of a nuclear power plant heat the nuclear reactor 1000 by directly attaching the heating component 310 to the metal outer surface of the nuclear reactor 1000; the metal is heated directly by heat conduction and can be powered on at any time, which effectively shortens the heating period and helps to improve the efficiency of the water pressure test. In addition, the heating component 310 includes a flexible heating element 1 that can be tightly attached to the outer surface of the nuclear reactor 1000, which is beneficial to increase the contact area and reduce the heat loss during heating; the protective layer 2 can improve the tensile strength of the entire heating component 310 and reduce the contact wear between the protective layer 2 and the metal outer surface, thereby improving the structural stability; the thermal insulation layer 3 can reduce the loss of heat generated by the flexible heating element 1 into the air, thereby improving the heating efficiency.

[0062] In some embodiments, the flexible heating element 1 is a silicone heating element or a heating element made of a ductile composite material. In this embodiment, the flexible heating element 1 is preferably a silicone heating element.

[0063] In some embodiments, the protective layer 2 is made of EPDM (Ethylene Propylene Diene Monomer) foam board, which has good tensile resistance, high buffer elasticity, high temperature resistance and flame retardancy. Then the protective layer 2 directly contacts the metal outer surface of the nuclear reactor 1000 to improve structural stability.

[0064] In some other embodiments, the insulation layer 3 adopts EPDM (Ethylene Propylene Diene Monomer) foam board; since the foam material contains a large amount of air or other gases, it is not easy to circulate, especially the closed-cell foam material, which has completely separated independent bubbles. The material can significantly slow down the conduction of heat, has an extremely low thermal conductivity coefficient, and good thermal insulation properties, making it an ideal thermal insulation material.

[0065] refer to Figure 4 、 Figure 5 、 Figure 6 In some embodiments, the heating component 310 further includes a heat reflecting film 4 , which is disposed between the flexible heating element 1 and the thermal insulation layer 3 .

[0066] Specifically, the heat-reflecting film 4 mainly reflects thermal radiation to prevent heat from being scattered into the air through radiation; the heat-reflecting film 4 is arranged on the side of the flexible heating element 1 away from the metal outer surface of the nuclear reactor 1000, and the flexible heating element 1 is attached to the metal outer surface for direct heating. The heat-reflecting film 4 can further reflect the heat generated by the flexible heating element 1 to the side of the metal outer surface, thereby reducing the loss of heat into the air and effectively improving the heating efficiency.

[0067] In some embodiments, the heat reflective film 4 is a mirror reflective film, such as an aluminum-plated reflective film or a pure aluminum reflective film, which has excellent corrosion resistance and reflectivity.

[0068] refer to Figure 4 In some embodiments, the heating component 310 further includes a magnetic element 5 located within the protective layer 2 .

[0069] As can be understood, the protective layer 2 is used to adhere to the outer surface of the metal. The protective layer 2 contains a magnetic element 5, which can be adsorbed by the metal to provide a magnetic attraction, so that the heating component 310 is tightly attached to the outer surface of the metal and the connection is stable. In this embodiment, the magnetic element 5 has good high temperature resistance, and the magnetic attraction is less affected by temperature. The magnetic element 5 can be a circular, rectangular, or oval magnet, etc.

[0070] Continue to refer Figure 4 In some embodiments, the magnetic element 5 is exposed outside the protective layer 2, and the magnetic element 5 can directly contact the outer surface of the metal, so that the magnetic attraction effect is better and the bonding force between the magnetic element 5 and the outer surface of the metal is greater;

[0071] In some embodiments, the flexible heating body 1 includes a heating plate 11 and a wrapping layer 12 respectively wrapped on opposite sides of the heating plate 11, and the protective layer 2 is arranged on the wrapping layer 12 on one side of the heating plate 11; the magnetic element 5 is arranged on the heating plate 11 and is embedded in the wrapping layer 12 and the protective layer 2 in sequence.

[0072] As can be understood, the heating element 11 is a metal heating element that generates heat when energized. In this embodiment, the wrapping layer 12 is made of silicone material that wraps around the heating element 11. That is, the flexible heating element 1 is a silicone heating element, which has the advantages of being waterproof, heat-resistant, and uniform, with fast heating speed and good heating efficiency. Furthermore, the silicone heating element has good flexibility and can be tightly adhered to the outer surface of the metal.

[0073] Specifically, the protective layer 2 and the thermal insulation layer 3 are respectively connected to the wrapping layer 12 on opposite sides of the flexible heating element 1, and the connection method can be but is not limited to gluing, bonding, hot melting, nail gun connection and the like.

[0074] The magnetic element 5 is arranged on the heating plate 11 so that the structure of the magnetic element 5 is supported firmly, and the magnetic element 5 is embedded in the protective layer 2. The magnetic element 5 can be close to the metal outer surface of the nuclear reactor 1000 to ensure the magnetic effect.

[0075] refer to Figure 7 、 Figure 8 In some embodiments, the heating plate 11 is provided with a mounting hole 6 for mounting the magnetic element 5 .

[0076] Specifically, a mounting hole 6 for mounting the magnetic element 5 is reserved on the heating plate 11 , and the magnetic element 5 can be directly mounted in the mounting hole 6 , which is convenient and quick to install.

[0077] The wrapping layer 12 and the protective layer 2 are correspondingly provided with via holes for accommodating the magnetic element 5 , so that the magnetic element 5 can be exposed outside the protective layer 2 .

[0078] In some embodiments, the magnetic element 5 is interference-fitted with the wall of the mounting hole 6 , so that the connection between the magnetic element 5 and the heating plate 11 is tight and stable, and the connection structure is more reliable.

[0079] In some other embodiments, the magnetic element 5 can be connected to the heating plate 11 and the protective layer 2 using, but not limited to, glue or adhesive, so that the connection structure between the magnetic element 5, the heating plate 11 and the protective layer 2 is stable.

[0080] Continue to refer Figure 7 、 Figure 8 In some embodiments, the heating plate 11 is provided with staggered slot structures 7 .

[0081] It can be understood that the shape of the heating plate 11 is designed to be a rectangular structure or an arc structure according to the steam generator 200 or the reactor pressure vessel 100, so that the heating component 310 can be better attached to the outer surface of the steam generator 200 or the reactor pressure vessel 100.

[0082] The groove structure 7 is distributed on the entire heating plate 11, which is conducive to the bending of the heating plate 11, so that the heating plate 11 can be better bent and attached to the outside of the steam generator 200 or the reactor pressure vessel 100; the heating plate 11 is closely attached to the metal outer surface, reducing the gap between the heating component 310 and the metal outer surface, thereby reducing heat damage and improving heating efficiency.

[0083] refer to Figure 1 In some embodiments, the heating component 310 further includes a connecting portion 300 electrically connected to the flexible heating element 1 , and the connecting portion 300 is configured to be connected to an external power source to supply power to the heating component 310 .

[0084] Specifically, the connecting part 300 is a power connection line, one end of the connecting part 300 is electrically connected to the heating plate 11 of the flexible heating element 1, and the other end of the connecting part 300 is connected to an external power source to energize and heat the heating plate 11.

[0085] In some embodiments, the heating system for water pressure testing of a nuclear power plant further includes a remote control terminal 320 that is communicatively connected to the heating component 310, and the connecting portion 300 is electrically connected to the remote control terminal 320, so that the start and stop of the heating component 310 and the heating power of the heating component 310 can be controlled through the remote control terminal 320, making the operation more flexible.

[0086] In some embodiments, the heating component 310 further includes a temperature sensor (not shown), which is disposed on any one of the heating sheet 11 , the wrapping layer 12 , and the protective layer 2 .

[0087] It is understandable that the temperature sensor is configured to detect the temperature of the metal outer surface in real time. Therefore, the temperature sensor is disposed on the side of the heating plate 11 close to the metal outer surface of the nuclear reactor 1000 .

[0088] Specifically, the temperature sensor is provided on the heating plate 11 .

[0089] The temperature sensor detects temperature and emits a temperature signal. The temperature sensor is in communication with a remote control terminal 320. The remote control terminal 320 is configured to control the heating power of the heating assembly 310 based on the relationship between the temperature signal and a preset temperature threshold. In this embodiment, for example, when the temperature of the metal outer surface of the nuclear reactor 1000 is detected to be below a preset temperature threshold, the remote control terminal 320 can increase the heating power of the heating assembly, thereby improving heating efficiency. When the temperature of the metal outer surface is detected to be greater than or equal to the preset temperature threshold, the remote control terminal 320 can reduce the heating power of the heating assembly 310, thereby lowering or maintaining the temperature of the metal outer surface. This helps conserve energy while ensuring the normal progress of the test. The remote control terminal 320 can be an on-site temperature control cabinet or a mobile computer terminal, etc., and is not specifically limited here.

[0090] The above are only preferred embodiments of the present application and are not intended to limit the present application. Any modifications, equivalent replacements, and improvements made within the spirit and principles of the present application should be included in the scope of protection of the present application.

Claims

1. A heating assembly for heating a metal to be heated; characterized in that: The heating component includes a flexible heating element and a protective layer and a heat-insulating layer respectively arranged on opposite sides of the flexible heating element; the protective layer is used to be attached to the outer surface of the metal to be heated.

2. The heating assembly according to claim 1, characterized in that The heating component further includes a heat reflecting film, which is arranged between the flexible heating element and the heat insulation layer.

3. The heating assembly according to claim 1, wherein The heating assembly also includes a magnetic element located within the protective layer.

4. The heating assembly according to claim 3, characterized in that The flexible heating element includes a heating plate and a wrapping layer respectively wrapped on opposite sides of the heating plate, and the protective layer is arranged on the wrapping layer on one side of the heating plate; the magnetic element is arranged on the heating plate and embedded in the wrapping layer and the protective layer in sequence.

5. The heating assembly according to claim 4, characterized in that The heating plate is provided with a mounting hole for mounting the magnetic element.

6. The heating assembly according to claim 4, characterized in that The heating plate is provided with staggered slot structures.

7. The heating assembly according to claim 4, characterized in that The heating component further includes a temperature sensor, which is disposed on any one of the heating sheet, the wrapping layer, and the protective layer.

8. The heating assembly according to claim 1, wherein: The heating component further includes a connecting portion electrically connected to the flexible heating element, and the connecting portion is configured to be connected to an external power source.

9. A heating system for water pressure testing in a nuclear power plant, characterized in that: include: A nuclear reactor and a heating assembly as described in any one of claims 1 to 8, wherein the protective layer of the heating assembly is configured to be adhered to the outer surface of the nuclear reactor; the nuclear reactor is in a steam generator and / or a reactor pressure vessel.

10. A heating system for a nuclear power plant hydrostatic test according to claim 9, characterized in that: The heating system for the nuclear power plant hydrostatic test further includes a remote control terminal in communication with the heating component.

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