Method, device and medium for testing leakage of boss head weld of nuclear power plant

Abstract

The present application relates to the technical field of nuclear power plant maintenance optimization, and particularly relates to a nuclear power plant BOSS head surfacing weld leakage test method, equipment and medium, the method comprising: receiving a test instruction for carrying out a leakage test on a nuclear power plant BOSS head after surfacing repair; preparing a BOSS head simulation pipe fitting containing four defects according to defect data, the BOSS head simulation pipe fitting being consistent with the size and material of the nuclear power plant BOSS head; carrying out a water-carrying and pressure-carrying surfacing operation on the weld area of the BOSS head simulation pipe fitting according to surfacing repair data; determining a leakage index of the BOSS head simulation pipe fitting after repair is completed; determining a leakage result according to the leakage index, and recording the leakage result as a leakage verification result of the nuclear power plant BOSS head after surfacing repair. The present application can determine the feasibility of repairing the nuclear power plant BOSS head by surfacing repair data, reduce the repair time and difficulty of the weld of the nuclear power plant BOSS head, ensure the overall construction period of the nuclear power plant unit overhaul, and ensure the safe operation of the nuclear power plant.

Description

Technical Field

[0001] This invention relates to the field of nuclear power plant maintenance and optimization technology, specifically to a method, equipment, and medium for testing leakage in the BOSS head weld seam of a nuclear power plant. Background Technology

[0002] Numerous BOSS (Special Bust Joint) structures are used in the main loop and secondary / tertiary component piping systems of nuclear power plants. These structures vary widely in size and are complex. Furthermore, the welds between the main and branch pipes of the BOSS head are subjected to the same temperature and pressure as the main pipe, making them prone to defects during manufacturing and operation. Failure and leakage of BOSS head welds can severely impact the safe operation of a nuclear power plant. This is especially true in the primary loop system, which contains radioactive media. Leaks of radioactive media are extremely difficult to repair, pose a high risk of contamination, and significantly affect the overall overhaul schedule. Therefore, conducting feasibility studies on the safe repair of BOSS head welds to ensure that repaired welds will not fail or leak again is a pressing issue that needs to be addressed. Summary of the Invention

[0003] This invention provides a method, equipment, and medium for testing the leakage of BOSS head weld seams in nuclear power plants, solving the problem of how to conduct feasibility tests for safe repair of BOSS head weld seams.

[0004] This invention provides a method for testing the leakage of weld seams in the BOSS head of a nuclear power plant, comprising:

[0005] The system receives a test instruction to conduct a leak test on the nuclear power plant BOSS head after weld repair. The test instruction includes defect data corresponding to four defects present on the nuclear power plant BOSS head, as well as weld repair data for repairing all defects on the nuclear power plant BOSS head. The nuclear power plant BOSS head includes a main pipe and branch pipes connected to the main pipe at a preset angle. The four defects are respectively located at the 0-degree, 90-degree, 180-degree, and 270-degree positions corresponding to the weld areas of the main pipe and the branch pipe.

[0006] Based on the defect data, a BOSS head simulation pipe fitting containing four of the defects is prefabricated, and the BOSS head simulation pipe fitting is consistent with the size and material of the nuclear power plant BOSS head.

[0007] Based on the weld overlay repair data, a water-cooled and pressurized weld overlay operation was performed on the weld area of ​​the BOSS head simulated pipe fitting to obtain a repaired BOSS head simulated pipe fitting.

[0008] Determine the leakage indicators of the repaired BOSS head simulated pipe fitting;

[0009] A leakage result is determined according to the leakage index, and the leakage result is recorded as a leakage verification result of the BOSS head of the nuclear power plant after the surfacing repair.

[0010] Optionally, the 0-degree position and the 180-degree position are arranged opposite to the axis of the mother pipe.

[0011] Optionally, each of the defects is arranged at a groove side of the weld region close to the branch pipe, a groove side of the weld region close to the mother pipe, or a throat of the weld region.

[0012] Optionally, the defect is a through hole with a preset diameter.

[0013] Before the water-carrying and pressure-carrying surfacing operation on the weld region of the BOSS head simulation pipe according to the surfacing repair data, the method comprises the following steps of:

[0014] The four through holes are respectively plugged by four sheets with a preset thickness.

[0015] Optionally, the preset diameter is 6 mm, and the preset thickness is 2 mm.

[0016] Optionally, the surfacing repair data comprises a surfacing layer number and water-carrying and pressure-carrying surfacing parameters corresponding to each of the surfacing layer numbers; the water-carrying and pressure-carrying surfacing parameters comprise welding material parameters, power polarity, welding current parameters, pulse frequency, duty cycle, tungsten electrode diameter, arc voltage, welding speed, maximum heat input, and interlayer temperature.

[0017] Optionally, when the surfacing layer number is a first layer, the water-carrying and pressure-carrying surfacing parameters corresponding to the first layer comprise:

[0018] The welding material diameter in the welding material parameters is 1.6 mm.

[0019] The power polarity is direct current reverse connection.

[0020] The peak value of the welding current parameters is 90 V, and the base value is 70 A.

[0021] The pulse frequency is 2.0 Hz.

[0022] The duty cycle is 60%.

[0023] The tungsten electrode diameter is 2.4.

[0024] The arc voltage is 9-12 V.

[0025] The welding speed is 32-71 mm / min.

[0026] The maximum heat input is 1400 J / mm.

[0027] The interlayer temperature is less than or equal to 100℃.

[0028] Optionally, when the number of layers of surfacing is the second layer, the water-cooling and pressure surfacing parameters corresponding to the second layer comprise:

[0029] The diameter of the welding material in the welding material parameter is 1.6 mm;

[0030] The power polarity is direct current reverse connection;

[0031] The peak value of the welding current parameter is 100V, and the base value is 75A;

[0032] The pulse frequency is 2.0Hz;

[0033] The duty cycle is 60%;

[0034] The diameter of the tungsten electrode is 2.4;

[0035] The arc voltage is 9-12V;

[0036] The welding speed is 32-54 mm / min;

[0037] The maximum heat input is 1800 J / mm;

[0038] The interlayer temperature is less than or equal to 100℃.

[0039] Optionally, when the number of layers of surfacing is one of the third layer to the fifth layer, the water-cooling and pressure surfacing parameters corresponding thereto comprise:

[0040] The diameter of the welding material in the welding material parameter is 1.6 mm;

[0041] The power polarity is direct current reverse connection;

[0042] The peak value of the welding current parameter is 100V, and the base value is 75A;

[0043] The pulse frequency is 2.0Hz;

[0044] The duty cycle is 60%;

[0045] The diameter of the tungsten electrode is 2.4;

[0046] The arc voltage is 9-12V;

[0047] The welding speed is 20-60 mm / min;

[0048] The maximum heat input is 2000 J / mm;

[0049] The interlayer temperature is less than or equal to 100℃.

[0050] Optionally, when the number of layers of surfacing is one of the sixth layer to the seventh layer, the water-cooling and pressure surfacing parameters corresponding thereto comprise:

[0051] The welding material parameter is that the welding material diameter is 1.6 mm;

[0052] The power polarity is direct current reverse connection;

[0053] The welding current parameter is that the peak value is 105 V and the base value is 85 A;

[0054] The pulse frequency is 2.0 Hz;

[0055] The duty cycle is 60%;

[0056] The tungsten electrode diameter is 2.4;

[0057] The arc voltage is 9-12 V;

[0058] The welding speed is 20-60 mm / min;

[0059] The maximum heat input is 2200 J / mm;

[0060] The interlayer temperature is less than or equal to 100 DEG C.

[0061] Optionally, the determining the leakage index of the repaired BOSS head simulation pipe fitting comprises:

[0062] determining a first leakage test index of the repaired BOSS head simulation pipe fitting through visual nondestructive testing and colored penetration nondestructive testing;

[0063] determining a second leakage test index of the repaired BOSS head simulation pipe fitting through metallographic testing;

[0064] determining the leakage index according to the first leakage test index and the second leakage test index.

[0065] Optionally, the first leakage test index comprises a water-pressure leakage index; and the second leakage test index comprises a cross-section metallographic crack index.

[0066] Optionally, the determining the leakage result according to the leakage index comprises:

[0067] when the water-pressure leakage index is no leakage and the cross-section metallographic crack index is no crack expansion in the cross-section metallography, confirming that the leakage result is no leakage;

[0068] when the water-pressure leakage index is leakage and the cross-section metallographic crack index is crack expansion in the cross-section metallography, confirming that the leakage result is leakage.

[0069] The application further provides a computer device, comprising a memory, a processor, and computer readable instructions stored in the memory and executable on the processor, wherein the processor executes the computer readable instructions to implement the BOSS head overlay weld leakage test method for nuclear power plants.

[0070] The application further provides a computer readable storage medium, which stores computer readable instructions, wherein the computer readable instructions are executed by a processor to implement the BOSS head overlay weld leakage test method for nuclear power plants.

[0071] The BOSS head overlay weld leakage test method for nuclear power plants, the device and the medium provided by the application receive a test instruction for performing a leakage test on a nuclear power plant BOSS head after overlay repair; the test instruction comprises defect data corresponding to four defects existing on the nuclear power plant BOSS head and overlay repair data for performing overlay repair on all defects of the nuclear power plant BOSS head; the nuclear power plant BOSS head comprises a mother pipe and a branch pipe connected to the mother pipe at a preset angle; the four defects are respectively arranged at 0-degree positions, 90-degree positions, 180-degree positions and 270-degree positions corresponding to weld regions of the mother pipe and the branch pipe; a BOSS head simulation pipe fitting comprising the four defects is prepared according to the defect data, the BOSS head simulation pipe fitting is consistent with the size and material of the nuclear power plant BOSS head; a water-carrying and pressure-carrying overlay operation is performed on a weld region of the BOSS head simulation pipe fitting according to the overlay repair data, to obtain a repaired BOSS head simulation pipe fitting; a leakage index of the repaired BOSS head simulation pipe fitting is determined; a leakage result is determined according to the leakage index, and the leakage result is recorded as a leakage verification result of the nuclear power plant BOSS head after the overlay repair.

[0072] The nuclear power plant BOSS head surfacing weld leakage test method in the application can first prepare a BOSS head simulation pipe according to the defect data in the test instruction before repairing the nuclear power plant BOSS head according to the surfacing repair data, and then perform water-carrying and pressure-carrying surfacing operation on the weld area of the BOSS head simulation pipe according to the surfacing repair data in the test instruction to obtain a repaired BOSS head simulation pipe, and then determine the leakage verification result of the nuclear power plant BOSS head according to the leakage index of the repaired BOSS head simulation pipe. In this way, according to the above leakage verification result, the feasibility of repairing the nuclear power plant BOSS head according to the surfacing repair data can be determined, that is, whether the nuclear power plant BOSS head repaired according to the surfacing repair data can be safe and leak-free after surfacing repair. In this way, the repair time and difficulty of the weld of the nuclear power plant BOSS head in the actual nuclear power plant overhaul process are reduced, the overall construction period of the nuclear power plant unit overhaul is ensured, the safety of the weld of the repaired nuclear power plant BOSS head is ensured, the radioactive medium in the nuclear power plant system such as the primary loop system pipeline is not leaked, and the safe operation of the nuclear power plant is ensured. BRIEF DESCRIPTION OF DRAWINGS

[0073] In order to more clearly illustrate the technical solutions of the embodiments of the application, the following will briefly introduce the drawings needed to be used in the description of the embodiments of the application. Obviously, the drawings in the following description are only some embodiments of the application, and other drawings can be obtained by those skilled in the art without creative labor.

[0074] Figure 1 is a flow chart of the nuclear power plant BOSS head surfacing weld leakage test method in an embodiment of the application;

[0075] Figure 2 is a cross-sectional structure schematic diagram of the BOSS head simulation pipe after the water-carrying and pressure-carrying surfacing operation in an embodiment of the application;

[0076] Figure 3 is a schematic diagram of a computer device in an embodiment of the application.

[0077] The reference signs in the specification are as follows:

[0078] 11, mother pipe; 12, branch pipe; 13, defect; 14, welding area. DETAILED DESCRIPTION

[0079] With reference to the accompanying drawings, the technical solutions in the embodiments of the present application will be clearly and completely described below, obviously, the described embodiments are some of the embodiments of the present application, rather than all the embodiments. Based on the embodiments in the present application, all other embodiments obtained by those skilled in the art without creative efforts belong to the protection scope of the present application.

[0080] In an embodiment, as shown in Figure 1 , a nuclear power plant BOSS head overlay welding seam leakage test method is provided, comprising the following steps S10-S50:

[0081] S10, receiving a test instruction for performing a leakage test on a nuclear power plant BOSS head after overlay repair; the test instruction contains defect data corresponding to four defects existing on the nuclear power plant BOSS head, and overlay repair data for performing overlay repair on all defects of the nuclear power plant BOSS head; as shown in Figure 2 , the nuclear power plant BOSS head comprises a parent pipe 11 and a branch pipe 12 connected to the parent pipe 11 at a preset angle (the preset angle refers to the included angle between the central axis of the parent pipe and the central axis of the branch pipe on the plane formed by the central axis of the parent pipe and the central axis of the branch pipe, that is, the central axis of the parent pipe and the central axis of the branch pipe intersect, and the preset angle is 90 degrees or less than 90 degrees); four defects (such as Figure 2 defects 13 in the figure) are respectively arranged at 0-degree, 90-degree, 180-degree and 270-degree positions corresponding to the weld seam areas of the parent pipe 11 and the branch pipe 12; wherein, the nuclear power plant BOSS head in the present application is a reinforced transition design, the welding form between the branch pipe 12 and the parent pipe 11 is a deposited welding, and the weld seam between the branch pipe 12 and the parent pipe 11 is a full penetration fillet weld.

[0082] In the present application, the overlay repair of the nuclear power plant BOSS head can be completed by performing water and pressure overlay welding operation according to the overlay repair data (including the number of overlay welding layers and the water and pressure overlay welding parameters), but before the operation, the overlay repair data needs to be verified for feasibility, that is, the subsequent steps S20-S50 are operated, and finally the leakage verification result of the nuclear power plant BOSS head after overlay repair is obtained. Therefore, the test instruction should be generated before the water and pressure overlay welding operation is performed according to the overlay repair data, and the above-mentioned defect data and overlay repair data need to be obtained first. Understandably, the defect data can refer to the historical defects actually detected on the nuclear power plant BOSS head by a preset detection method, or can be defects that have not occurred according to the requirements.

[0083] Understandably, the 0-degree position and the 180-degree position are arranged opposite to the axis of the mother pipe 11. That is, in this embodiment, two defects need to be arranged opposite to the axis of the mother pipe 11, and the two defects are arranged on opposite sides of the branch pipe 12, that is, one position on the weld area opposite to the axis of the mother pipe 11 and on the branch pipe 12 is taken as the 0-degree position, and the other position on the weld area opposite to the 0-degree position and on the branch pipe 12 is taken as the 180-degree position; and the other two defects are arranged on the line perpendicular to the axis of the mother pipe 11, and the two defects are also arranged on opposite sides of the branch pipe 12 (that is, the 90-degree position and the 270-degree position).

[0084] Further, each of the defects is arranged at the branch pipe 12 side of the groove of the weld area, the mother pipe 11 side of the groove of the weld area, or the throat of the weld area. The weld area refers to the weld between the mother pipe 11 and the branch pipe 12, and the weld between the branch pipe 12 and the mother pipe 11 is a full penetration fillet weld. Arranging different defects at different positions of the weld area can better simulate various defects at different positions of the weld area of the BOSS head of the nuclear power plant, and thus the overlay repair of defects at different positions can be completely verified.

[0085] The overlay repair data includes the number of overlay layers and water-pressure overlay parameters corresponding to each of the overlay layers. The water-pressure overlay parameters include but are not limited to welding material parameters, power polarity, welding current parameters, pulse frequency, duty cycle, tungsten electrode diameter, arc voltage, welding speed, maximum heat input, and interlayer temperature. In the present application, the water-pressure overlay operation is performed through the following specific overlay repair data, so that the final leakage test result is more stable and reliable.

[0086] When the number of overlay layers is the first layer, the water-pressure overlay parameters corresponding to the first layer include that the welding material parameter has a welding material diameter of 1.6 mm; the power polarity is direct current reverse connection; the welding current parameter has a peak value of 90 V and a base value of 70 A; the pulse frequency is 2.0 Hz; the duty cycle is 60%; the tungsten electrode diameter is 2.4; the arc voltage is 9-12 V; the welding speed is 32-71 mm / min; the maximum heat input is 1400 J / mm; and the interlayer temperature is less than or equal to 100℃.

[0087] When the number of the surfacing layers is the second layer, the water-cooled and pressure-welded surfacing parameters corresponding to the second layer include that the welding material parameter has a welding material diameter of 1.6 mm; the power polarity is direct current reverse connection; the welding current parameter has a peak value of 100 V and a base value of 75 A; the pulse frequency is 2.0 Hz; the duty cycle is 60%; the tungsten electrode diameter is 2.4; the arc voltage is 9-12 V; the welding speed is 32-54 mm / min; the maximum heat input is 1800 J / mm; and the interlayer temperature is less than or equal to 100℃.

[0088] When the number of the surfacing layers is one of the third layer to the fifth layer, the water-cooled and pressure-welded surfacing parameters corresponding thereto include that the welding material parameter has a welding material diameter of 1.6 mm; the power polarity is direct current reverse connection; the welding current parameter has a peak value of 100 V and a base value of 75 A; the pulse frequency is 2.0 Hz; the duty cycle is 60%; the tungsten electrode diameter is 2.4; the arc voltage is 9-12 V; the welding speed is 20-60 mm / min; the maximum heat input is 2000 J / mm; and the interlayer temperature is less than or equal to 100℃.

[0089] When the number of the surfacing layers is one of the sixth layer to the seventh layer, the water-cooled and pressure-welded surfacing parameters corresponding thereto include that the welding material parameter has a welding material diameter of 1.6 mm; the power polarity is direct current reverse connection; the welding current parameter has a peak value of 105 V and a base value of 85 A; the pulse frequency is 2.0 Hz; the duty cycle is 60%; the tungsten electrode diameter is 2.4; the arc voltage is 9-12 V; the welding speed is 20-60 mm / min; the maximum heat input is 2200 J / mm; and the interlayer temperature is less than or equal to 100℃.

[0090] S20, according to the defect data pre-preparation contains four BOSS head simulation pipe fittings of the defects, the BOSS head simulation pipe fittings are consistent with the size and material of the nuclear power plant BOSS head;Wherein, the BOSS head simulation pipe fittings also include the mother pipe 11, the branch pipe 12 and the weld area connected between the mother pipe 11 and the branch pipe 12, the BOSS head simulation pipe fittings can completely simulate the nuclear power plant BOSS head to present its actual various operating states (such as operating or overlaying repair in the water and pressure state or other states). The defect data corresponds to four defects;Four defects are respectively arranged at the 0 degree position, the 90 degree position, the 180 degree position and the 270 degree position corresponding to the weld area of the mother pipe 11 and the branch pipe 12 of the BOSS head simulation pipe fittings. Further, each of the defects is arranged at the groove of the weld area close to the branch pipe 12 side, the groove of the weld area close to the mother pipe 11 side or the throat of the weld area. Understandably, in the present application, the 0 degree position, the 90 degree position, the 180 degree position and the 270 degree position corresponding to the weld area are respectively provided with defects, according to the historical data of the weld defects obtained in the actual use process and the pipe size of the mother pipe 11 and the branch pipe 12, it is determined that only one defect can be arranged at each position, so that the accurate test result can be simulated.

[0091] Understandably, as shown in the figure, Figure 2 The defect 13 is a through hole with a preset diameter;As preferred, the preset diameter is 6mm;Wherein, if the through hole with a preset diameter of 6mm on the BOSS head simulation pipe fittings can be verified, that is, it represents that other forms and sizes of weld defects actually possible in the same position corresponding to the welding area 14 on the nuclear power plant BOSS head can also be repaired by overlaying with the same overlaying repair data and will not leak and so on. Therefore, the through hole with a preset diameter of 6mm is used as the defect in the present application.

[0092] S30, according to the overlaying repair data, the weld area of the BOSS head simulation pipe fittings is operated with water and pressure overlaying, and the repaired BOSS head simulation pipe fittings are obtained.

[0093] In the step S30, before the weld area of the BOSS head simulation pipe fittings is operated with water and pressure overlaying according to the overlaying repair data, it includes: four pieces of thin plates with a preset thickness are used to block four through holes respectively. As preferred, the preset thickness is 2mm. Understandably, one thin plate can be used to block one through hole, and the blocking mode can be that the thin plate is welded around the through hole, so that the thin plate can block the through hole, and then the overlaying is further carried out on the basis of the thin plate, so that the strength of the overlaying repair can be improved.

[0094] S40, determining the leakage index of the repaired BOSS head simulation pipe fitting; further, the step S40 comprises:

[0095] determining the first leakage test index of the repaired BOSS head simulation pipe fitting by visual non-destructive testing and colored penetration non-destructive testing; wherein the first leakage test index comprises but is not limited to water pressure leakage index (including leakage and no leakage); for example, the first leakage test index can also include external defect display index (including no defect display and defect display), internal surface metal slagging index (including internal surface metal slagging phenomenon or no slagging phenomenon) and the like.

[0096] determining the second leakage test index of the repaired BOSS head simulation pipe fitting by metallographic detection; the second leakage test index comprises but is not limited to cross-section metallographic crack index (including no crack extension in cross-section metallographic and crack extension in cross-section metallographic). For example, the second leakage test index also includes weld fusion index (including good weld fusion and poor weld fusion), hardening index (including no hardening structure and hardening structure), oxidation index (including no abnormal oxidation on the inner surface of the pipe or abnormal oxidation on the inner surface of the pipe) and the like. Understandably, the above-mentioned visual non-destructive testing, colored penetration non-destructive testing and metallographic detection technology all belong to the technology known by those skilled in the art, which will not be described here.

[0097] determining the leakage index according to the first leakage test index and the second leakage test index. That is, the leakage index is generated according to the first leakage test index and the second leakage test index, which at least contains water pressure leakage index (including leakage and no leakage) and cross-section metallographic crack index (including no crack extension in cross-section metallographic and crack extension in cross-section metallographic). In the present application, the leakage index can also be composed of other indexes in the first leakage test index and the second leakage test index according to the demand, and other indexes related to the possibility of leakage can also be additionally added, such as, the leakage index can also include penetration index (when the leakage index includes penetration index, it is set that only the penetration index also satisfies penetration less than 1.1 mm, and the leakage result can be no leakage); the leakage index can also include deformation index (when the leakage index includes deformation index, it is set that only the deformation index also satisfies deformation less than 4.6 mm, and the leakage result can be no leakage); in this way, the leakage result can be further determined in step S50 according to the above-mentioned leakage index.

[0098] S50, determining a leakage result according to the leakage indicators, and recording the leakage result as a leakage verification result of the BOSS head of the nuclear power plant after the overlay repair. That is, according to the leakage result, the leakage verification result of the BOSS head of the nuclear power plant after the overlay repair can be obtained. According to the leakage test result, it can be determined whether the overlay repair data can be safely used to complete the overlay repair of the BOSS head of the nuclear power plant, that is, the leakage test result is the evaluation result of the feasibility of the overlay repair of the BOSS head of the nuclear power plant by the overlay repair data.

[0099] In the step S50, the leakage result is determined according to the leakage indicators, including:

[0100] When the water-pressure leakage indicator is no leakage and the cross-section metallographic crack indicator is no crack expansion in the cross-section metallograph, it is determined that the leakage result is no leakage. That is, when the water-pressure leakage indicator is no leakage and the cross-section metallographic crack indicator is no crack expansion in the cross-section metallograph, the leakage result is no leakage, which indicates that the overlay repair data corresponding to the set of leakage indicators can be safely used to complete the overlay repair of the BOSS head of the nuclear power plant, that is, the overlay repair is feasible.

[0101] When the water-pressure leakage indicator is leakage and the cross-section metallographic crack indicator is crack expansion in the cross-section metallograph, it is determined that the leakage result is leakage. That is, when the water-pressure leakage indicator is leakage and the cross-section metallographic crack indicator is crack expansion in the cross-section metallograph, the leakage result is leakage, which indicates that the overlay repair data corresponding to the set of leakage indicators may cause leakage accident during the overlay repair of the BOSS head of the nuclear power plant, and the overlay repair scheme is not safe, that is, the overlay repair is not feasible.

[0102] In an embodiment, the leakage indicators include a water-pressure leakage indicator, an outer surface defect display indicator, an inner surface metal slagging indicator, a cross-section metallographic crack indicator, a weld bead fusion indicator, a hardening indicator, an oxidation indicator, a penetration indicator, and a deformation indicator. When the leakage indicators satisfy the following requirements at the same time, it is determined that the leakage result is no leakage: the water-pressure leakage indicator is no leakage, the outer surface defect display indicator is no defect display, the inner surface metal slagging indicator is no metal slagging phenomenon in the inner surface, the cross-section metallographic crack indicator is no crack expansion in the cross-section metallograph, the weld bead fusion indicator is good weld bead fusion, the hardening indicator is no hardening structure, the oxidation indicator is no abnormal oxidation in the inner surface of the pipeline, the penetration indicator is less than 1.1 mm, and the deformation indicator is less than 4.6 mm. When one of the above leakage indicators is not satisfied, it is considered that the leakage result is leakage, which may cause leakage risk.

[0103] The nuclear power plant BOSS head surfacing weld leakage test method in the application can first prepare a BOSS head simulation pipe according to the defect data in the test instruction before repairing the nuclear power plant BOSS head according to the surfacing repair data, and then perform a water-carrying and pressure-carrying surfacing operation on the weld area of the BOSS head simulation pipe according to the surfacing repair data in the test instruction to obtain a repaired BOSS head simulation pipe, and then determine the leakage verification result of the nuclear power plant BOSS head according to the leakage index of the repaired BOSS head simulation pipe. In this way, according to the leakage verification result, the feasibility of repairing the nuclear power plant BOSS head according to the surfacing repair data can be determined, that is, whether the repair of the nuclear power plant BOSS head according to the surfacing repair data can make the weld of the nuclear power plant BOSS head after surfacing repair safe and leak-free. In this way, the repair time and difficulty of the weld of the nuclear power plant BOSS head in the actual nuclear power plant overhaul process are reduced, the overall construction period of the nuclear power plant unit overhaul is ensured, the safety of the nuclear power plant BOSS head after repair is ensured, the radioactive medium in the nuclear power plant system such as the primary system pipeline is not leaked, and the safe operation of the nuclear power plant is ensured.

[0104] In one embodiment, a computer device, which can be a server, is provided, and an internal structure diagram of the computer device can be as shown in Figure 3 The computer device includes a processor, a memory, a network interface and a database connected through a system bus. The processor of the computer device is configured to provide computing and control capabilities. The memory of the computer device includes a non-volatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, computer readable instructions and a database. The internal memory provides an environment for the operating system and computer readable instructions in the non-volatile storage medium. The computer readable instructions are executed by the processor to implement the above-mentioned nuclear power plant BOSS head surfacing weld leakage test method.

[0105] In one embodiment, a computer readable storage medium is provided, and the computer readable storage medium stores computer readable instructions, and the computer readable instructions are executed by the processor to implement the above-mentioned nuclear power plant BOSS head surfacing weld leakage test method.

[0106] Those skilled in the art can understand that all or part of the processes in the above-mentioned embodiment methods can be completed by instructing relevant hardware through computer readable instructions, and the computer readable instructions can be stored in a non-volatile computer readable storage medium. When the computer readable instructions are executed, the processes of the above-mentioned embodiments of the methods can be included. Any reference to memory, storage, database or other medium used in each embodiment of the present application can include non-volatile and / or volatile memory. Non-volatile memory can include read-only memory (ROM), programmable ROM (PROM), electrically programmable ROM (EPROM), electrically erasable programmable ROM (EEPROM) or flash memory. Volatile memory can include random access memory (RAM) or external cache memory. As an illustration but not limitation, RAM is available in various forms, such as static RAM (SRAM), dynamic RAM (DRAM), synchronous DRAM (SDRAM), double data rate SDRAM (DDR SDRAM), enhanced SDRAM (ESDRAM), synchronous link DRAM (SLDRAM), memory bus direct RAM (RDRAM), direct memory bus dynamic RAM (DRDRAM), and memory bus dynamic RAM (RDRAM), etc.

[0107] Those skilled in the art can clearly understand that, for the convenience and brevity of description, only the division of the above-mentioned functional units or modules is exemplified, and in actual application, the above-mentioned functions can be completed by different functional units or modules according to needs, that is, the internal structure of the system is divided into different functional units or modules to complete all or part of the functions described above.

[0108] The above-mentioned embodiments are only used to illustrate the technical solutions of the present application, but not to limit it; although the present application has been described in detail with reference to the foregoing embodiments, those skilled in the art should understand that the technical solutions recorded in the foregoing embodiments can be modified, or some technical features can be replaced by equivalents; and these modifications or replacements do not make the essence of the corresponding technical solutions deviate from the spirit and scope of the technical solutions of the embodiments of the present application, and should be included in the protection scope of the present application.

Claims

1. A method of testing a BOSS head overlay weld of a nuclear power plant for leaks, the method comprising: applying a vacuum to the BOSS head overlay weld; and applying a pressurized fluid to the BOSS head overlay weld. The method comprises the following steps: receiving a test instruction for a leakage test on a nuclear power plant BOSS head after surfacing repair; the test instruction contains defect data corresponding to four defects on the nuclear power plant BOSS head, and surfacing repair data for surfacing repair of all defects on the nuclear power plant BOSS head; the nuclear power plant BOSS head comprises a main pipe and a branch pipe connected to the main pipe at a preset angle; the four defects are respectively arranged at 0-degree positions, 90-degree positions, 180-degree positions and 270-degree positions corresponding to the weld regions of the main pipe and the branch pipe; the 0-degree position and the 180-degree position are arranged opposite to the axis of the main pipe; wherein, one position opposite to the axis of the main pipe and on the weld region is the 0-degree position, and another position opposite to the 0-degree position and on the other side of the branch pipe and belonging to the weld region is the 180-degree position; the 90-degree position and the 270-degree position are both on a line perpendicular to the axis of the main pipe, and the 90-degree position and the 270-degree position are respectively arranged on the weld regions on opposite sides of the branch pipe; the defects are through holes with a preset diameter; preparing a BOSS head simulation pipe fitting containing the four defects according to the defect data, the BOSS head simulation pipe fitting being consistent with the size and material of the nuclear power plant BOSS head; blocking the four through holes by four sheets with a preset thickness, respectively, and performing water-carrying and pressure-carrying surfacing operation on the weld regions of the BOSS head simulation pipe fitting according to the surfacing repair data to obtain a repaired BOSS head simulation pipe fitting; determining a leakage index of the repaired BOSS head simulation pipe fitting; determining a leakage result according to the leakage index, and recording the leakage result as a leakage verification result of the nuclear power plant BOSS head after surfacing repair.

2. The method for testing the leakage of the head overlay weld of the BOSS of the nuclear power plant according to claim 1, characterized in that, Each of the defects is arranged at a bevel groove side of the weld region close to the branch pipe, a bevel groove side of the weld region close to the main pipe, or a throat of the weld region.

3. The method for testing the head weld of a nuclear power plant BOSS head for leaks as recited in claim 1, wherein, The preset diameter is 6 mm, and the preset thickness is 2 mm.

4. The method for testing the head weld of a nuclear power plant BOSS head for leaks as recited in claim 1, wherein, The surfacing repair data comprises: a number of surfacing layers and water-carrying and pressure-carrying surfacing parameters corresponding to each of the number of surfacing layers; the water-carrying and pressure-carrying surfacing parameters comprise welding material parameters, power polarity, welding current parameters, pulse frequency, duty cycle, tungsten electrode diameter, arc voltage, welding speed, maximum heat input and interlayer temperature.

5. The method for testing the head weld of a nuclear power plant BOSS head for leaks as recited in claim 4, wherein When the number of surfacing layers is the first layer, the water-carrying and pressure-carrying surfacing parameters corresponding to the first layer comprise: the welding material parameter is a welding material diameter of 1.6 mm; the power polarity is direct current reverse connection; the welding current parameter is a peak value of 90 V and a base value of 70 A; the pulse frequency is 2.0 Hz; the duty cycle is 60%; the tungsten electrode diameter is 2.4; the arc voltage is 9-12 V; the welding speed is 32-71 mm / min; the maximum heat input is 1400 J / mm; the interlayer temperature is less than or equal to 100℃.

6. The method for testing the head weld of a nuclear power plant BOSS head for leaks as recited in claim 4, wherein When the number of surfacing layers is the second layer, the water-carrying and pressure-carrying surfacing parameters corresponding to the second layer comprise: the welding material parameter is a welding material diameter of 1.6 mm; the power polarity is direct current reverse connection; The peak value of the welding current parameter is 100 V, and the base value is 75 A; The pulse frequency is 2.0 Hz; The duty cycle is 60%; The tungsten electrode diameter is 2.4; The arc voltage is 9-12 V; The welding speed is 32-54 mm / min; The maximum heat input is 1800 J / mm; The interlayer temperature is less than or equal to 100℃.

7. The method for testing the head weld of a nuclear power plant BOSS head for leaks as recited in claim 4, wherein, When the overlaying layer number is one of the third layer to the fifth layer, the water and pressure overlaying parameters corresponding thereto include: The welding material parameter is that the welding material diameter is 1.6 mm; The power supply polarity is direct current reverse connection; The peak value of the welding current parameter is 100 V, and the base value is 75 A; The pulse frequency is 2.0 Hz; The duty cycle is 60%; The tungsten electrode diameter is 2.4; The arc voltage is 9-12 V; The welding speed is 20-60 mm / min; The maximum heat input is 2000 J / mm; The interlayer temperature is less than or equal to 100℃.

8. The method for testing the head weld of a nuclear power plant BOSS head for leaks as recited in claim 4, wherein, When the overlaying layer number is one of the sixth layer to the seventh layer, the water and pressure overlaying parameters corresponding thereto include: The welding material parameter is that the welding material diameter is 1.6 mm; The power supply polarity is direct current reverse connection; The peak value of the welding current parameter is 105 V, and the base value is 85 A; The pulse frequency is 2.0 Hz; The duty cycle is 60%; The tungsten electrode diameter is 2.4; The arc voltage is 9-12 V; The welding speed is 20-60 mm / min; The maximum heat input is 2200 J / mm; The interlayer temperature is less than or equal to 100℃.

9. The method for testing the head weld of a nuclear power plant BOSS head for leaks as recited in claim 1, wherein, The determination of the leakage index of the repaired BOSS head simulation pipe includes: ​ The first leakage test index of the repaired BOSS head simulation pipe is determined by visual nondestructive testing and colored penetration nondestructive testing; The second leakage test index of the repaired BOSS head simulation pipe is determined by metallographic detection; The leakage index is determined according to the first leakage test index and the second leakage test index.

10. The method for testing the head weld of a nuclear power plant BOSS head for leaks as recited in claim 9, wherein, The first leakage test index includes a water and pressure leakage index; and the second leakage test index includes a cross-section metallographic crack index.

11. The method for testing the head weld of a nuclear power plant BOSS head for leaks as recited in claim 10, wherein, The determination of the leakage result according to the leakage index includes: ​ When the water and pressure leakage index is no leakage, and the cross-section metallographic crack index is no crack expansion in the cross-section metallography, it is confirmed that the leakage result is no leakage; When the water and pressure leakage index is leakage, and the cross-section metallographic crack index is crack expansion in the cross-section metallography, it is confirmed that the leakage result is leakage.

12. A computer device comprising a memory, a processor, and computer readable instructions stored in the memory and executable on the processor, wherein, The processor executes the computer readable instructions to implement the BOSS head overlaying weld leakage test method of the nuclear power station according to any one of claims 1-11.

13. A computer-readable storage medium having stored computer-readable instructions, wherein, The computer readable instructions are executed by the processor to implement the BOSS head overlaying weld leakage test method of the nuclear power station according to any one of claims 1-11.

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