Strength testing system and methods for cables and protective measures within the reactor

Abstract

This invention relates to a strength testing system and method for cables and protective measures within a reactor. The system includes a jet fluid simulation unit providing fluid at set temperature and pressure, and a sample fixing platform for securing the cables and protective measures. By conducting jet impact tests on the cables under set fluid conditions, both in their exposed state and with protective measures in place, the critical distance between the cable and the jet nozzle is determined based on the cable surface damage condition, under both exposed and different protective measures conditions, at the point of fluid impact-induced damage. By testing the impact of different protective measures on the strength performance of the cable sample under set fluid conditions, the critical distance between the cable sample and the jet nozzle at which surface cracking just occurs is determined, thus providing a reference for the installation distance requirements of the cable sample.

Description

Technical Field

[0001] This invention relates to the field of nuclear energy equipment technology, specifically to a system and method for testing the strength of cables and protective measures inside a reactor. Background Technology

[0002] The statements in this section are merely background information related to the present invention and do not necessarily constitute prior art.

[0003] Cables within a nuclear power reactor are responsible for transmitting control signals and power energy to the reactor equipment. For the safe operation of the reactor, it is necessary to ensure that the cables can still maintain normal signal and power transmission functions for a certain period of time in the event of a reactor accident. In the event of an accident, the cables are often subjected to the impact of high-temperature and high-pressure fluids. Therefore, it is necessary to conduct strength tests to test the cables' ability to withstand the impact of high-temperature and high-pressure fluids under different protective measures.

[0004] Existing technology can utilize high-pressure pumps to generate high-temperature, high-pressure fluids, and then use these fluids to conduct impact strength tests on structural components within the reactor. While such strength testing systems can be applied to cable strength testing, the inherent strength of the cable is determined after manufacturing. Different installation methods, protective measures, and variations in the distance between the cable and high-pressure pipelines due to different installation positions within the reactor all affect the cable's strength performance. Furthermore, this effect is amplified under accident conditions. Therefore, current strength testing systems lack corresponding testing methods to determine this influence. Summary of the Invention

[0005] To address the technical problems mentioned above, this invention provides a strength testing system and method for cables and protective measures within a reactor. The system utilizes a plunger pump to simulate high-temperature, high-pressure fluid under accident conditions and impacts cable samples through a jet nozzle. Under set impact conditions, the system tests the influence of different protective measures on the strength performance of the cable samples, thereby determining the critical distance between the cable sample and the jet nozzle at which structural damage just occurs. This provides a reference for the installation conditions of the cable samples.

[0006] To achieve the above objectives, the present invention adopts the following technical solution:

[0007] The first aspect of the present invention provides a method for strength testing of cables and protective measures within a reactor, comprising the following steps:

[0008] The test cable sample was connected between two columns, and the working fluid was pressurized and heated to the set pressure and temperature.

[0009] Under the set fluid pressure, temperature and flow rate, and initial jet spacing, the bare cable sample was subjected to a jet impact test. After each test, the structural state of the cable sample was obtained. By comparing it with the structural state before the test, the structural damage state of the cable sample was determined.

[0010] Repeated tests were conducted by changing the jet spacing until the cable sample under test showed no structural damage after a set number of consecutive tests at a single jet spacing. The jet spacing at this point is the critical spacing at which the cable breaks when exposed to the impact of fluid at a set temperature, pressure and flow rate.

[0011] At the critical spacing, different protective measures were added to the same type of test cable samples, and jet impact tests were conducted under the corresponding fluid pressure, temperature and flow rate. The test was repeated by changing the jet spacing until the test cable sample showed no structural damage when the set number of consecutive tests was conducted under a single jet spacing. The jet spacing at this point is the critical spacing at which the cable will break when subjected to the fluid impact at the set temperature, pressure and flow rate under the corresponding protective measures.

[0012] Furthermore, before the test cable sample was connected to the column, its initial structural state was obtained by scanning with an electron microscope.

[0013] Furthermore, after each test, the structural condition of the cable sample under test is obtained, and by comparing it with the structural condition before the test, the structural damage state of the cable sample under test is determined; specifically:

[0014] After each test, the integrity of the tested cable sample is inspected by visual inspection to determine the damage status of the surface;

[0015] If there is no surface damage, the impacted area is scanned with an electron microscope to obtain the structural state after the test. By comparing it with the structural state before the test, it is determined that the test cable sample has internal tissue damage but has not caused external damage.

[0016] Test cable samples with surface damage determined by visual inspection and test cable samples with internal damage determined by electron microscopy are both considered to be damaged test cable samples.

[0017] Furthermore, repeated experiments were conducted by changing the jet spacing. Specifically, the jet spacing was based on the diameter D of the jet nozzle, with 1D as the jet spacing. The jet impact experiment was repeated each time the 1D spacing was changed.

[0018] Furthermore, protective measures include a cable tray / trough connecting the two columns and a matching cover plate covering the surface of the cable tray / trough, protecting the test cable sample within the space formed by the cable tray / trough and the cover plate.

[0019] Furthermore, the protective measures also include a metal flexible tube fitted over the outer surface of the cable. The test cable sample is fitted with the metal flexible tube, and end plates are provided on both columns. The end plates are connected to the ends of the metal flexible tube through connectors, so that the test cable sample is protected by the metal flexible tube.

[0020] A second aspect of the present invention provides a strength testing system for cables and protective measures within a reactor, comprising:

[0021] The jet fluid simulation unit provides fluid at a set temperature and pressure through a plunger pump and a preheating section installed on the pipeline, and then ejects it through a jet nozzle;

[0022] The sample holder has a sample fixing platform for fixing cables and protective measures. The sample fixing platform has at least two sets of columns arranged in parallel. The columns are equipped with clips. The test area of ​​the cable sample is arranged between the two sets of columns, and the non-test area is fixed to the columns by clips.

[0023] Furthermore, the jet fluid simulation unit includes a water storage tank, a shut-off valve, a plunger pump, and a jet nozzle connected in sequence by pipes. A preheating section is provided in the pipe between the plunger pump and the jet nozzle. The jet nozzle faces the sample holder. Temperature and pressure detection sensors are provided on the pipe.

[0024] Furthermore, the sample holder includes a sample fixing platform, a triangular support frame, and a base. The sample fixing platform is movably connected to the triangular support frame and faces the jet nozzle. The triangular support frame is movably connected to the base and is used to adjust the distance between the sample fixing platform and the jet nozzle.

[0025] Furthermore, when the outer diameter of the test cable sample is smaller than the set size, the non-tested sections at both ends are wrapped around the column surface a set number of times and then fixed with clips; when it is not smaller than the set size, it is fixed to the column surface with multiple clips.

[0026] Compared with existing technologies, one or more of the above technical solutions have the following beneficial effects:

[0027] 1. By changing the conditions of jet impact and the type of protective measures, the critical spacing at which the tested cable sample will be damaged when subjected to fluid impacts of different temperatures, pressures, and flow rates under exposed conditions and with different protective measures is obtained. The critical spacing serves as a recommendation for the installation spacing between the exposed cable and accident risk points during the reactor design and installation stages, preventing cable damage from jet impacts in the event of a breach. The critical spacing corresponding to different protective measures can help designers and installers provide a basis for optional protective measures when the cable must be laid close to accident risk points (such as high-pressure pipelines).

[0028] 2. The strength testing process takes into account the influence of various conditions on the cable's strength performance. Through testing, the cable is covered in the bare state and in the state with different protective measures, as well as in the state with different jet pressures, temperatures and flow rates. The final jet spacing can reflect the influence of different conditions on the cable's strength performance, thus providing a basis for selecting the cable protection type and installation location during the reactor design and installation phase.

[0029] 3. Regarding the cable structure, the issue of the cable potentially detaching from the sample holder when subjected to fluid impact was considered. This involved a structure that wraps around the column and uses clips to strengthen the connection between the cable's non-test area and the sample holder, preventing detachment during strength testing and affecting subsequent test results. Attached Figure Description

[0030] The accompanying drawings, which form part of this invention, are used to provide a further understanding of the invention. The illustrative embodiments of the invention and their descriptions are used to explain the invention and do not constitute an improper limitation of the invention.

[0031] Figure 1 This is a structural schematic diagram of a reactor cable and protective measure strength testing system provided in one or more embodiments of the present invention;

[0032] Figure 2 This is a schematic diagram of the mating structure between the cable non-tested area and the column provided in one or an embodiment of the present invention;

[0033] Figure 3 This is a schematic diagram of a snap-fit ​​structure provided in one or an embodiment of the present invention;

[0034] Figure 4 This is a schematic diagram of the structure of the sample holder mounting bridge provided in one or an embodiment of the present invention;

[0035] Figure 5 This is a schematic diagram of the structure of the sample holder mounting cover provided in one or an embodiment of the present invention;

[0036] Figure 6 This is a schematic diagram of the cooperation structure between the metal flexible tube for installing the sample cable and the sample holder provided in one or an embodiment of the present invention.

[0037] In the diagram: 1. Water tank, 2. Shut-off valve, 3. Plunger pump, 4. Preheating section, 5. Jet nozzle, 6. Sample fixing platform, 7. Column, 8. Cable, 9. Clip, 10. Cable tray / trough, 11. Cover plate. Detailed Implementation

[0038] The present invention will be further described below with reference to the accompanying drawings and embodiments.

[0039] It should be noted that the following detailed descriptions are exemplary and intended to provide further illustration of the invention. Unless otherwise specified, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention pertains.

[0040] Terminology Explanation:

[0041] To ensure that radioactive materials do not leak into the environment, nuclear reactors are a key design feature. Generally, nuclear power plants have three safety barriers.

[0042] The first safety barrier consists of fuel pellets and fuel cladding. Fuel pellets are typically made of sintered uranium dioxide ceramic, whose microporous structure largely isolates them from the outside environment, allowing them to trap most of the radioactive material produced by nuclear fission. The fuel pellets are then encased in cladding made of zirconium alloy or stainless steel to form fuel element rods.

[0043] The second safety barrier consists of a pressure vessel and a closed primary loop system. The pressure vessel is used to enclose the reactor core, which consists of nuclear fuel.

[0044] The third safety barrier is the containment building (reactor building), which is generally a prestressed reinforced concrete structure up to 1 meter thick, with a steel lining on the inner surface, providing excellent sealing performance. The containment building also houses a safety injection system, a containment spray system, a hydrogen removal system, an air purification and cooling system, etc., to cope with possible extreme accidents.

[0045] The various systems within the safety barrier require power supply and transmission of control signals, which imposes corresponding design requirements on the cables in terms of electrical continuity, pressure resistance, and temperature resistance.

[0046] Furthermore, as described in the background section, to ensure that cables can maintain normal operation for a sufficient period of time under the impact of high-temperature and high-pressure fluids during an accident, it is necessary to consider the cable's strength limit under accident conditions during the design phase and determine a reasonable installation location based on the layout of equipment within the reactor (e.g., a certain distance from potential accident risk points, such as high-pressure pipelines) to mitigate or reduce the impact of fluids on the cables, thereby extending the cable's operational time under accident conditions. Existing technology can utilize high-pressure pumps to generate high-temperature and high-pressure fluids and use these fluids to conduct impact strength tests on structural components within the reactor.

[0047] When this type of strength testing system is applied to cable strength testing, the strength of the cables inside the reactor is already determined after manufacturing. However, different installation methods, different protective measures, and different installation spacing within the reactor will affect the strength performance of the cables. Moreover, this effect will be amplified under accident conditions. This type of strength testing system lacks corresponding testing and detection methods to determine this effect.

[0048] Therefore, the following embodiments provide a strength testing system and method for cables and protective measures within a reactor. A high-pressure pump is used to simulate high-temperature and high-pressure fluid under accident conditions, and the cable sample is impacted through a jet nozzle. Under the set impact conditions, the influence of different protective measures on the strength performance of the cable sample is tested, thereby determining the critical distance between the cable sample and the jet nozzle without surface cracking, thus providing a reference for the installation conditions of the cable sample.

[0049] Example 1:

[0050] During a reactor accident, cables are subjected to the impact of high-temperature, high-pressure fluids. For example, when a rupture occurs in the primary loop piping of a pressurized water reactor, water at 15.5 MPa and temperatures exceeding 270°C will spray out from the rupture, forming a high-temperature, high-pressure jet. This fluid will impact surrounding cables. Therefore, this embodiment tests the withstand capability of cable trays, cable ducts, and reinforced metal flexible conduits under the impact of high-temperature, high-pressure jets, providing a reasonable reference for cable installation methods and locations.

[0051] like Figure 1 As shown, the strength testing system for cables and protective measures inside the reactor includes a water tank 1, a shut-off valve 2, a plunger pump 3 and a jet nozzle 5 connected in sequence by pipes. A preheating section 4 is provided in the pipe between the plunger pump 3 and the jet nozzle 5. The jet nozzle 5 faces the sample holder. Temperature, pressure and flow detection sensors are provided on the pipe.

[0052] Water tank 1 is used to store the working fluid for testing; shut-off valve 2 is used to control the flow of the working fluid into plunger pump 3; plunger pump 3 is used to pressurize the working fluid to the target pressure; preheating section 4 is used to heat the working fluid to the target temperature; sample holder is used to fix cable sample and its reinforcement sample.

[0053] A flow regulating valve is installed on the pipeline to regulate the flow rate of the jet nozzle 5.

[0054] The plunger pump 3 is a high-pressure stage, which can precisely control the pressure and ensure that the pressure in front of the jet nozzle 5 does not fluctuate significantly.

[0055] Preheating section 4 is a multi-stage heating system that combines AC and DC heating, with the final stage being DC heating.

[0056] The sample holder includes a sample holder 6, a triangular support frame and a base. The sample holder is movably connected to the triangular support frame and faces the jet nozzle 5. The base is fixed to the ground and the triangular support frame is movably connected to the base.

[0057] The sample fixing stage 6 is movably connected to the triangular support frame to adjust the horizontal position between the sample fixing stage and the jet nozzle 5. The specific structure for adjusting the horizontal position is not limited, and the horizontal position can be adjusted by a slide rail structure.

[0058] The triangular support frame is movably connected to the base to adjust the distance between the sample fixing stage and the jet nozzle 5. The specific structure for adjusting the distance is not limited. For example, the two can be movably connected by setting corresponding strip holes in the area where the base and the triangular support frame contact each other. By adjusting the overlap of the strip holes in the base and the triangular support frame, the jet distance can be adjusted within the length range of the strip holes. After adjustment, it is locked by fasteners to eliminate the influence of different initial distances from the sample surface to the jet nozzle caused by different sizes of the test cable sample.

[0059] In this embodiment, the sample fixing platform is welded to the triangular support frame, and the welding height is determined by the height of the jet nozzle 5.

[0060] The sample fixing stage 6 has at least two sets of columns 7 arranged side by side. Each column 7 has a clip 9. The cable 8, serving as the sample, is arranged horizontally between the two sets of columns 7. The area between the two sets of columns 7 is the test area, receiving the impact of the high-temperature, high-pressure fluid ejected from the jet nozzle 5. The portions fixed to the columns 7 at both ends are the non-test area. To ensure that the cable 8 in the test area does not detach from the sample fixing stage under the fluid impact, it is necessary to ensure that the portions of the cable 8 in the non-test area are reliably fixed to the columns 7. This embodiment adopts the following... Figure 2 In the structure shown, the cable 8 in the non-test area is wrapped around the column 7, and the cable 8 is locked to the column 7 at the end by a buckle 9.

[0061] The structure of buckle 9 is as follows Figure 3 As shown, the device includes a U-shaped locking bracket and a fastener passing through the locking bracket. The U-shaped opening of the locking bracket connects to the surface of the column 7. After the end of the cable 8 is wound around the column 7 a predetermined number of times, it passes through the area between the surface of the column 7 and the U-shaped opening of the locking bracket. Through the tightening action of the fastener, the end of the cable 8 is brought into contact with the surface of the column 7. At the same time, to ensure that the surface of the cable 8 is not damaged by the tightening action of the fastener, the end of the fastener is provided with a flat abutment plate.

[0062] The cable 8 in the non-test area is spirally wound with the column 7. When subjected to fluid impact, the cable 8 tends to move away from the jet nozzle 5. The spiral winding allows the cable 8 to obtain the largest possible contact area with the surface of the column 7, preventing the cable 8 from detaching from the sample holder. At the same time, the spiral winding also allows the cable 8 to gradually tighten the column 7, further preventing the cable 8 from detaching from the sample holder. In addition, the end of the cable 8 is abutted against the surface of the column 7 by a clip 9, which further prevents the cable 8 from detaching from the sample holder. Through this structure, it is ensured that the test area of ​​the cable 8 is not easily detached from the sample holder when subjected to fluid impact, thereby obtaining reliable test results.

[0063] When the diameter of the cable 8 exceeds a certain value, it may be difficult to wrap around the post 7 due to its own hardness. At this time, multiple clips 9 can be used to directly abut and fix the non-tested area of ​​the cable 8 to the post 7.

[0064] A cable tray / trough can also be connected between the two columns 7. The cable tray / trough is used to simulate the cable tray / trough that accommodates the cables 8 in a real reactor.

[0065] A cover plate can also be connected between the two columns 7. The cover plate is used to simulate the components that cover the surface of the cable tray / trough in a real reactor, so that the cable 8 is protected by the space formed by the cable tray / trough and the cover plate. The cover plate and the cable tray / trough offset some of the impact from the high temperature and high pressure fluid, so that the cable tray / trough and the cover plate form a protective measure for the cable 8.

[0066] A metal flexible conduit can also be connected between the two uprights 7. The cable 8 is fitted inside the metal flexible conduit. The two uprights 7 are equipped with end plates, which are connected to both ends of the metal flexible conduit through gland connectors, so that the cable 8 is protected by the metal flexible conduit. The metal flexible conduit offsets some of the impact from the high temperature and high pressure fluid, so that the metal flexible conduit forms a protective measure for the cable 8.

[0067] The strength testing system described above is designed for the sample cable and takes into account the possibility of the cable detaching from the sample holder when subjected to fluid impact. It involves a structure that is wrapped around the column and uses clips to strengthen the connection between the non-tested area of ​​the cable and the sample holder, thus preventing detachment during the strength test and affecting subsequent test results.

[0068] Example 2:

[0069] The method for testing the strength of cables and protective measures within a reactor includes the following steps:

[0070] The test cable sample was connected between two columns, and the working fluid was pressurized and heated to the set pressure and temperature.

[0071] Under the set fluid pressure, temperature and flow rate, and initial jet spacing, the bare cable sample was subjected to a jet impact test. After each test, the structural state of the cable sample was obtained. By comparing it with the structural state before the test, the structural damage state of the cable sample was determined.

[0072] Repeated tests were conducted by changing the jet spacing until the cable sample under test showed no structural damage after a set number of consecutive tests at a single jet spacing. The jet spacing at this point is the critical spacing at which the cable breaks when exposed to the impact of fluid at a set temperature, pressure and flow rate.

[0073] At the critical spacing, different protective measures were added to the same type of test cable samples, and jet impact tests were conducted under the corresponding fluid pressure, temperature and flow rate. The test was repeated by changing the jet spacing until the test cable sample showed no structural damage when the set number of consecutive tests was conducted under a single jet spacing. The jet spacing at this point is the critical spacing at which the cable will break when subjected to the fluid impact at the set temperature, pressure and flow rate under the corresponding protective measures.

[0074] Connect the cable tray / trough between the two uprights 7, such as Figure 4 The test cable sample 8 shown is located in the cable tray / trough 10 and connected between the two columns 7.

[0075] When fixing the cable 8, avoid excessive stretching to prevent interference with the test results. For example, the cable sample under test should not be straightened directly on the cable tray / trough. Instead, the cable that has been straightened beforehand should be cut according to the distance between the two columns 7 and then fixed.

[0076] In this embodiment, for cables with an outer diameter less than 20mm, the cable is wound around the column 7 multiple times in the non-tested section and then secured using clips 9. If a cable with an outer diameter of not less than 20mm is difficult to wind around the column 7 due to rigidity issues, it is directly secured to the surface of the column 7 using multiple clips 9.

[0077] The cable under test after installation is the same as the actual reactor scenario, with a certain degree of freedom. It can move slightly within a certain range to cope with thermal expansion and contraction and to ensure that there is no positional shift or detachment during the jet impact.

[0078] After the cable 8 under test is installed, the working fluid is heated and pressurized until the set pressure and temperature are reached, and jet impact is performed. The jet pressure, jet temperature and jet flow rate are recorded during the test.

[0079] A jet impact test was conducted under set pressure, temperature and flow rate. Before the test, the impacted part of the test cable sample was scanned by electron microscope to obtain a record of its complete structure.

[0080] After each test, the integrity of the test cable sample is first checked by visual inspection to determine whether there is any cracking damage on the surface. If there is no obvious cracking damage, the impacted part is scanned by electron microscopy to obtain its structural state after the test. By comparing it with the complete structure before the test, the test cable sample that may have internal tissue damage but has not caused obvious external cracking damage is identified, thus identifying the damaged test cable sample.

[0081] If the surface of the test cable sample shows cracking damage or internal tissue damage that may pose a risk to subsequent use after scanning with an electron microscope, the jet spacing is changed. The jet spacing is based on the jet nozzle diameter D, starting from 1D, and the spacing is changed by 1D each time (i.e., 1D, 2D, 3D up to nD), and the jet impact test is repeated.

[0082] In this embodiment, each jet spacing is tested three times. After each test, the damage on the surface of the test cable sample is checked until the surface of the test cable sample is undamaged after three consecutive tests at a single spacing. The jet spacing xD at this time is the critical spacing at which the cable will break when exposed to the impact of fluid at a set temperature, pressure and flow rate. This critical spacing serves as a recommendation for the installation spacing between the exposed cable and the accident risk point during the design phase, to prevent the cable from being damaged by jet impact in a breakage accident.

[0083] When a test cable sample is subjected to jet impact in an exposed state at a certain jet spacing and causes cracking damage on its surface, two kinds of reinforced protection measures are added to the same type of test cable sample, and then the jet impact test is carried out again at the same spacing under the same jet parameters (meaning that the pressure, temperature, flow rate and duration during the jet are the same).

[0084] Enhanced protective measures include:

[0085] ① Cable tray / trough + cover plate: Cover plate 11 is placed over the opening of the cable tray / trough 10, so that the cable sample under test is protected by the space formed by the cable tray / trough and the cover plate. The cable tray / trough 10 and the cover plate 11 first withstand the fluid impact, such as... Figure 5 As shown;

[0086] ② Metal flexible hose: The test cable sample is covered with a metal flexible hose, and the metal flexible hose first withstands the fluid impact.

[0087] The fixing method of the metal flexible hose differs from the direct fixing of the test cable sample. A steel plate is used to simulate the end plate of the electrical equipment. The steel plate is connected to the column 7 and a hole is made in it. The steel plate and the column can be connected by welding. After the metal flexible hose passes through the hole in the steel plate, a gland connector is used to connect the end of the metal flexible hose to the steel plate. The area between the two steel plates is the test area, so that the cable 8 is protected by the metal flexible hose. The metal flexible hose offsets part of the impact of the high temperature and high pressure fluid, disperses the impact force of the jet, and prevents the cable 8 from being directly impacted by the jet.

[0088] Gland connectors are existing technology and are devices used to secure and protect wires and cables, typically placed at the cable ends, for example... Figure 6 The installation method is shown.

[0089] After the test, the cable structure was visually inspected or scanned with an electron microscope to compare it with the unprotected test cable sample to determine the protective capability of different protective measures. In this embodiment, each jet spacing was tested three times under different protective measures. After each test, the surface damage of the test cable sample was checked until the surface of the test cable sample was undamaged after three consecutive repeated tests at a single spacing. The jet spacings yD and zD at this point are the critical spacings at which the cable breaks when subjected to fluid impact at a set temperature, pressure, and flow rate under the protective measures of cable trays / troughs + covers and metal hoses. These critical spacings provide optional protective measures during the actual design and installation stages when the cable must be laid close to accident risk points (such as high-pressure pipelines) to prevent damage to the cable from jet impact in the event of a breakage.

[0090] In practical applications, several samples can be taken from a specific type of cable to prepare test specimens, which are then divided into three groups: exposed state group, protective measure group 1 (cable tray / trough + cover plate), and protective measure group 2 (metal flexible conduit). The aforementioned strength tests are then performed on each group.

[0091] By changing the conditions of jet impact and the type of protective measures, the ability of the sample cable to withstand fluid impacts of different temperatures, pressures, and flow rates under exposed conditions and with different protective measures is obtained. The resulting test data can help designers determine the critical distance between the cable and the fluid outlet under different jet impact conditions and protective measures, and thus serve as the basis for selecting the cable protection type and installation spacing during the design phase.

[0092] The above description is merely a preferred embodiment of the present invention and is not intended to limit the invention. Various modifications and variations can be made to the present invention by those skilled in the art. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of the present invention should be included within the scope of protection of the present invention.

Claims

1. A method for testing the strength of cables and protective measures within a reactor, characterized in that, Includes the following steps: The test cable sample was connected between two columns, and the working fluid was pressurized and heated to the set pressure and temperature. Under the set fluid pressure, temperature and flow rate, and initial jet spacing, the bare cable sample was subjected to a jet impact test. After each test, the structural state of the cable sample was obtained. By comparing it with the structural state before the test, the structural damage state of the cable sample was determined. Repeated tests were conducted by changing the jet spacing until the test cable sample showed no structural damage after a set number of consecutive tests under a single jet spacing. At this point, the jet spacing was the critical spacing at which the cable would break when exposed to the impact of fluid at a set temperature, pressure and flow rate. At the critical spacing, different protective measures were added to the same type of test cable samples, and jet impact tests were conducted under the corresponding fluid pressure, temperature and flow rate. The test was repeated by changing the jet spacing until the test cable sample showed no structural damage after a set number of consecutive tests at a single jet spacing. The jet spacing at this point is the critical spacing at which the cable breaks when subjected to fluid impact at a set temperature, pressure and flow rate under the influence of the corresponding protective measures.

2. The method for testing the strength of reactor cables and protective measures as described in claim 1, characterized in that, Before the test cable sample is connected to the column, its initial structural state is obtained by scanning with an electron microscope.

3. The method for testing the strength of reactor cables and protective measures as described in claim 1, characterized in that, After each test, the structural condition of the cable sample under test is obtained, and the structural damage state of the cable sample is determined by comparing it with the structural condition before the test; specifically: After each test, the integrity of the tested cable sample is inspected by visual inspection to determine the damage status of the surface; If there is no surface damage, the impacted area is scanned with an electron microscope to obtain the structural state after the test. By comparing it with the structural state before the test, it is determined that the test cable sample has internal tissue damage but has not caused external damage. Test cable samples with surface damage determined by visual inspection and test cable samples with internal damage determined by electron microscopy are both considered to be damaged test cable samples.

4. The method for testing the strength of reactor cables and protective measures as described in claim 1, characterized in that, Repeated experiments were conducted by changing the jet spacing. Specifically, the jet spacing was based on the diameter D of the jet nozzle, with 1D as the jet spacing. The jet impact experiment was repeated each time the 1D spacing was changed.

5. The method for testing the strength of reactor cables and protective measures as described in claim 1, characterized in that, The protective measures include a cable tray / trough connecting the two columns and a matching cover plate covering the surface of the cable tray / trough, and the test cable sample is protected by the space formed by the cable tray / trough and the cover plate.

6. The method for testing the strength of reactor cables and protective measures as described in claim 1, characterized in that, The protective measures also include a flexible metal tube fitted over the outer surface of the cable. The test cable sample is fitted with the flexible metal tube, and end plates are provided on both columns. The end plates are connected to the ends of the flexible metal tube through connectors, so that the test cable sample is protected by the flexible metal tube.

7. A strength testing system for reactor cables and protective measures implementing the method of any one of claims 1-6, characterized in that, include: The jet fluid simulation unit provides fluid at a set temperature and pressure through a plunger pump and a preheating section installed on the pipeline, and then ejects it through a jet nozzle; The sample holder has a sample fixing platform for fixing the test cable sample and protective measures. The sample fixing platform has at least two sets of columns arranged in parallel. The columns are equipped with buckles. The test area of ​​the test cable sample is arranged between the two sets of columns, and the non-test area is fixed to the columns by the buckles.

8. The strength testing system for reactor cables and protective measures as described in claim 7, characterized in that, The jet fluid simulation unit includes a water storage tank, a shut-off valve, a plunger pump, and a jet nozzle connected in sequence by pipes. A preheating section is provided in the pipe between the plunger pump and the jet nozzle. The jet nozzle faces the sample holder. Temperature and pressure detection sensors are provided on the pipe.

9. The strength testing system for reactor cables and protective measures as described in claim 7, characterized in that, The sample holder includes a sample fixing platform, a triangular support frame, and a base. The sample fixing platform is movably connected to the triangular support frame and faces the jet nozzle. The triangular support frame is movably connected to the base and is used to adjust the distance between the sample fixing platform and the jet nozzle.

10. The strength testing system for reactor cables and protective measures as described in claim 7, characterized in that, When the outer diameter of the test cable sample is smaller than the set size, the non-tested sections at both ends are wrapped around the column surface a set number of times and then fixed with clips; when it is not smaller than the set size, it is fixed to the column surface with multiple clips.

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