CN214748697U - Nuclear power station stabiliser electric heater leakproofness test device - Google Patents
Nuclear power station stabiliser electric heater leakproofness test device Download PDFInfo
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- CN214748697U CN214748697U CN202120682237.8U CN202120682237U CN214748697U CN 214748697 U CN214748697 U CN 214748697U CN 202120682237 U CN202120682237 U CN 202120682237U CN 214748697 U CN214748697 U CN 214748697U
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Abstract
The utility model belongs to the technical field of mechanical assembly, concretely relates to nuclear power station stabiliser electric heater leakproofness test device, include: the gasket testing device comprises a tool assembly, two end socket assemblies, a plurality of gasket testing assemblies and a plurality of supporting assemblies, wherein the tool assembly is integrally of a hollow cylindrical structure, and two ends of the tool assembly are respectively in threaded connection with the end socket assemblies; the outer surface of the cylinder of the tool assembly is also welded with a plurality of gasket test assemblies; and the plurality of supporting components are welded on the outer surface of the cylinder of the tool component at the same side. The device has delicate structure and convenient use, can truly simulate the field condition, and can carry out strength and sealing tests on the voltage stabilizer electric heater and the electric heater sealing gasket in two different forms.
Description
Technical Field
The utility model belongs to the technical field of mechanical assembly, concretely relates to nuclear power station stabiliser electric heater leakproofness test device.
Background
The voltage stabilizer is used as one of main equipment of a loop system of the nuclear power plant and mainly has the function of establishing and maintaining loop pressure during the starting period of a unit; compensating volume change of a primary circuit coolant caused by temperature change during the running of the unit, limiting fluctuation of primary circuit pressure caused by temperature change, and avoiding boiling of the coolant in a reactor; the steam-water balance in the voltage stabilizer is kept through the spraying and electric heater, the pressure of the primary loop is limited within a design range, and the overpressure of the primary loop is prevented; the primary circuit pressure is maintained or reduced during expected operating events, design-basis events, and over-design-basis accident conditions.
The electric heater of the voltage stabilizer is an important component for keeping the steam-water balance in the voltage stabilizer, and the installation and use effects of the electric heater of the voltage stabilizer determine the operation reliability of the voltage stabilizer. Each voltage stabilizer of the VVER type nuclear power unit is provided with 28 groups of electric heaters, the original electric heater body and the sealing gasket thereof are produced in Russia, and the defects of long supply period, high purchase price and high failure rate exist, so that a certain nuclear power station in China carries out domestic manufacturing substitution on the electric heaters of the voltage stabilizers of the nuclear power unit No. 1-4 and the sealing gaskets of the voltage stabilizers of the nuclear power unit No. 3 and 4. After the electric heater is manufactured, a series of tests such as a strength test, a sealing test and the like are required to verify the performance of the electric heater. In the past, all performance tests of the Russian power supply heater are performed by Russian manufacturers during the manufacturing of the electric heater, and China does not have the performance test device of the electric heater.
Therefore, in order to perform various performance tests on the domestic electric heater and better meet the test requirements of different sealing electric heaters of each unit, a sealing performance test device for the domestic nuclear power station voltage stabilizer electric heater needs to be designed to solve the problem that the domestic electric heater cannot perform the performance test
SUMMERY OF THE UTILITY MODEL
The utility model discloses in to prior art, provide a nuclear power station stabiliser electric heater leakproofness test device for solve and to carry out the technical problem that intensity test, leakproofness are experimental to the electric heater after the current localization.
The technical scheme of the utility model:
a nuclear power station stabiliser electric heater leakproofness test device includes: the gasket testing device comprises a tool assembly, two end socket assemblies, a plurality of gasket testing assemblies and a plurality of supporting assemblies, wherein the tool assembly is integrally of a hollow cylindrical structure, and two ends of the tool assembly are respectively in threaded connection with the end socket assemblies; the outer surface of the cylinder of the tool assembly is also welded with a plurality of gasket test assemblies; and the plurality of supporting components are welded on the outer surface of the cylinder of the tool component at the same side.
The frock subassembly includes: the device comprises a tool barrel, a hot circulating water inlet pipe, a hot circulating water outlet pipe, an exhaust pipe and a drain pipe; a hot circulating water inlet pipe, a hot circulating water outlet pipe and an exhaust pipe are respectively welded on the same side of the circumferential outer surface of the tool cylinder; a drain pipe is welded on the circumferential outer surface of the tool cylinder body and is welded on one side opposite to the hot circulating water inlet pipe, the hot circulating water outlet pipe and the exhaust pipe; flanges are respectively arranged at two ends of the tool cylinder.
The head subassembly still includes: the tool comprises a tool end socket, a lifting lug, a plurality of bolts A and nuts A; the tool sealing head is connected with the lifting lugs in a threaded mode and is connected with flanges at two ends of the tool barrel through bolts A and nuts A.
The gasket test assembly also comprises a flange support, a flange cover, a plurality of bolts B and nuts B; the flange support is connected with the outer surface of the tool cylinder in a welding mode, and the flange support is fixedly connected with the flange cover through a plurality of bolts B and nuts B in a threaded mode.
The support assembly further comprises: a support rod and a foundation bolt; one end of the supporting rod is connected with the outer surface of the tool barrel in a welded mode, the other end of the supporting rod is provided with an anchor bolt, and the supporting rod is fixedly connected with the ground through the anchor bolt.
The utility model has the advantages that:
the utility model provides a nuclear power station stabiliser electric heater leakproofness test device, this device structure is exquisite, and convenient to use can the true simulation field condition. The device can be used for testing the strength and the sealing performance of the voltage stabilizer electric heater and the sealing gasket of the electric heater in two different forms, can verify the using effect of the electric heater and the sealing gasket, can also be used for checking the parts of the electric heater through tests, timely finds the hidden danger and the defects of the electric heater, and repairs the possible problems, thereby solving the problem that the performance of the voltage stabilizer electric heater of the nuclear power unit cannot be verified domestically, improving the reliability and the stability of the electric heater in the field work, and laying a solid foundation for the smooth development of the operation and the maintenance work of the voltage stabilizer electric heater.
Drawings
FIG. 1 is a schematic view of the overall structure of a device for testing the sealing performance of an electric heater of a voltage stabilizer of a nuclear power station designed by the utility model;
FIG. 2 is a schematic view of the seal head assembly structure in the tightness test device of the present invention
FIG. 3 is a schematic view of a tooling assembly structure in the tightness test device of the present invention
Fig. 4 is a schematic structural diagram of a gasket testing assembly in the tightness testing apparatus of the present invention.
The device comprises a 1-end socket assembly, a 2-tooling assembly, a 3-gasket testing assembly, a 4-supporting assembly, a 101-tooling end socket, 102-lifting lugs, 103-bolts A, 104-nuts A, 201-tooling cylinders, 202-hot circulating water inlet pipes, 203-hot circulating water outlet pipes, 204-exhaust pipes, 205-drain pipes, 301-flange supports, 302-flange covers, 303-bolts B, 304-nuts B, 401-supporting rods and 402-foundation bolts.
Detailed Description
The sealing performance testing device for the electric heater of the voltage stabilizer of the nuclear power station of the present invention is described in detail with reference to the accompanying drawings and embodiments.
The utility model discloses a nuclear power station stabiliser electric heater leakproofness test device, include: the device comprises a tool assembly 2, two end socket assemblies 1, a plurality of gasket test assemblies 3 and a plurality of support assemblies 4, wherein the tool assembly 2 is integrally of a hollow cylindrical structure, the number of the end socket assemblies 1 is two, and two ends of the tool assembly 2 are respectively in threaded connection with one end socket assembly 1; the outer surface of the cylinder of the tool assembly 2 is also welded with a plurality of gasket test assemblies 3; and the plurality of supporting components 4 are welded on the outer surface of the cylinder of the tool component 2 at the same side.
The flange sealing form of the seal head component 1 arranged on the left side of the tool component 2 is a non-coplanar tongue-and-groove type double-channel sealing structure, and is the same as the flange sealing form of the electric heater of the unit voltage stabilizer 1 and the unit voltage stabilizer 2 in the nuclear power station to be tested. The flange sealing form of the end socket assembly 1 arranged on the right side of the tooling assembly 2 is a coplanar tongue-and-groove type double-channel sealing structure, and is the same as the flange sealing form of the electric heater of the unit voltage stabilizer of No. 3 and No. 4 of the Tianwan to be tested. Each tooling head 101 is fixed with a lifting lug 102, the lifting lug 102 is perpendicular to the ground, the lifting lug 102 can be used for lifting the whole experimental device, and the head is connected with the tooling when a test is not performed, so that foreign matters are prevented from entering the head cylinder;
the tool assembly 2 comprises: the device comprises a tool cylinder 201, a hot circulating water inlet pipe 202, a hot circulating water outlet pipe 203, an exhaust pipe 204 and a sewage discharge pipe 205; a hot circulating water inlet pipe 202, a hot circulating water outlet pipe 203 and an exhaust pipe 204 are respectively welded on the same side of the circumferential outer surface of the tool cylinder 201; a sewage discharge pipe 205 is welded on the circumferential outer surface of the tool cylinder 201, and the sewage discharge pipe 205 is welded on one side opposite to the hot circulating water inlet pipe 202, the hot circulating water outlet pipe 203 and the exhaust pipe 204; flanges are respectively arranged at two ends of the tool cylinder 201.
When a thermal cycle experiment is carried out, the tool end socket is removed, the electric heater is installed on one side of the tool cylinder 201, thermal cycle water enters the whole tool cylinder 201 through the thermal cycle water inlet pipe 202 and flows out of the cylinder through the thermal cycle water outlet pipe 203; when a hydraulic pressure strength test is carried out, the hot circulating water outlet pipe 203 is sealed, water enters the whole cylinder from the hot circulating water inlet pipe 202 and is gradually boosted to the pressure required by the strength test for carrying out the strength test, the exhaust pipe is used for exhausting in the water inlet process of the tool cylinder, and the drain pipe is used for draining water and discharging sewage after the test;
the gasket test assembly 3 further comprises a flange support 301, a flange cover 302, a plurality of bolts B303 and nuts B304; the flange support 301 is connected with the outer surface of the tool cylinder 201 in a welding mode, and the flange support 302 is fixedly connected with the flange cover 302 through a plurality of bolts B303 and nuts B304 in a threaded mode.
The localization gasket is placed in a sealing groove of a flange in the gasket test assembly 3, the flange cover 302 and the flange support 301 are tightly pressed by using a bolt B303 and a nut B304, and the performance of the localization sealing gasket is verified by applying certain water pressure to the device.
The support assembly 4 further comprises: a support bar 401 and an anchor bolt 402; one end of the supporting rod 401 is connected with the outer surface of the tool cylinder 201 in a welding mode, the other end of the supporting rod 401 is provided with an anchor bolt 402, and the supporting rod 401 is fixedly connected with the ground through the anchor bolt 402. The support assembly 4 is used for supporting and fixing the whole test device.
Adopt the utility model provides a device for nuclear power station stabiliser electric heater leakproofness is experimental, mainly used stabiliser domestic electric heater, seal gasket's leakproofness is experimental, carries out stabiliser electric heater test process, include following step:
the method comprises the following steps: in a non-working state, the tooling seal heads 101 on two sides of the seal head assembly 1 are connected with the tooling cylinder 201 and are in a sealing state to prevent foreign matters from entering the whole test device, at the moment, the whole test device is moved to a corresponding working position through the lifting lugs 102 on the tooling seal heads 101, and the whole test device is fixed by using foundation bolts 402 on the supporting assembly 4;
step two: the electric heater sealing performance and strength tests are carried out, the sealing gasket performance tests are hydraulic tests, when the tests are carried out, firstly, the tool end socket 101 on one side to be tested is dismantled, the electric heater to be tested is connected with the flange on the side, the electric heater is installed in place according to the torque required by the tests, the flange cover in the gasket test assembly 3 is dismantled, and after the gasket to be tested is installed in place, the flange cover is installed again according to the torque required by the tests;
step three: then the exhaust pipe 204 is opened, and the sewage draining pipe 205 is closed; the hot circulating water inlet pipe 202 is connected with a pressurizing pipeline and a pressure gauge, the hot circulating water outlet pipe 203 is connected with a water outlet pipeline, and water with the same temperature in the working state of the pressure stabilizer is continuously pumped into the test device;
when water in the device overflows from the exhaust pipe, the exhaust pipe is sealed to establish pressure in the device, water is continuously injected into the test device to increase the pressure to the test required pressure, the test device simulates the real working states of the electric heater and the sealing gasket, and whether the sealing performance of the electric heater is qualified or not can be judged by observing the parts such as the electric heater body, the sealing surface and the pressure gauge.
The above detailed description of the embodiments of the present invention is not limited to the above examples, and various changes can be made without departing from the spirit of the present invention within the knowledge range of those skilled in the art.
Claims (6)
1. The utility model provides a nuclear power station stabiliser electric heater leakproofness test device which characterized in that includes: the gasket testing device comprises a tool assembly (2), two seal head assemblies (1), a plurality of gasket testing assemblies (3) and a plurality of supporting assemblies (4), wherein the tool assembly (2) is integrally of a hollow cylindrical structure, and two ends of the tool assembly (2) are respectively in threaded connection with the seal head assemblies (1); the outer surface of the cylinder of the tool assembly (2) is also welded with a plurality of gasket test assemblies (3); the supporting components (4) are welded on the outer surface of the cylinder of the tool component (2) at the same side.
2. The device for testing the sealing performance of the electric heater of the voltage stabilizer of the nuclear power plant as claimed in claim 1, wherein: the tool assembly (2) comprises: the device comprises a tool cylinder (201), a hot circulating water inlet pipe (202), a hot circulating water outlet pipe (203), an exhaust pipe (204) and a sewage discharge pipe (205); a hot circulating water inlet pipe (202), a hot circulating water outlet pipe (203) and an exhaust pipe (204) are respectively welded on the same side of the circumferential outer surface of the tool cylinder body (201); a sewage discharge pipe (205) is further welded on the circumferential outer surface of the tool cylinder (201), and the sewage discharge pipe (205) is welded on one side opposite to the hot circulating water inlet pipe (202), the hot circulating water outlet pipe (203) and the exhaust pipe (204); flanges are respectively arranged at two ends of the tool cylinder (201).
3. The device for testing the sealing performance of the electric heater of the voltage stabilizer of the nuclear power plant as claimed in claim 2, wherein: the seal head assembly (1) further comprises: the tool comprises a tool end enclosure (101), a lifting lug (102), a plurality of bolts A (103) and nuts A (104); the tool sealing head (101) is in threaded connection with the lifting lug (102), and the tool sealing head (101) is connected with flanges at two ends of the tool cylinder body (201) through a bolt A (103) and a nut A (104).
4. The device for testing the sealing performance of the electric heater of the voltage stabilizer of the nuclear power plant as claimed in claim 3, wherein: the gasket test assembly (3) further comprises a flange support (301), a flange cover (302), a plurality of bolts B (303) and nuts B (304); the outer surface welded connection of flange support (301) and frock barrel (201), flange support (301) and flange lid (302) are through a plurality of bolt B (303) and nut B (304) screw thread fixed connection.
5. The device for testing the sealing performance of the electric heater of the voltage stabilizer of the nuclear power plant as claimed in claim 4, wherein: the support assembly (4) further comprises: a support rod (401) and an anchor bolt (402); one end of the supporting rod (401) is connected with the outer surface of the tool barrel (201) in a welding mode, the other end of the supporting rod (401) is provided with an anchor bolt (402), and the supporting rod (401) is fixedly connected with the ground through the anchor bolt (402).
6. The device for testing the sealing performance of the electric heater of the voltage stabilizer of the nuclear power plant as claimed in claim 5, wherein: the number of the supporting components (4) is two.
Priority Applications (1)
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CN202120682237.8U CN214748697U (en) | 2021-04-02 | 2021-04-02 | Nuclear power station stabiliser electric heater leakproofness test device |
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CN202120682237.8U CN214748697U (en) | 2021-04-02 | 2021-04-02 | Nuclear power station stabiliser electric heater leakproofness test device |
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2021
- 2021-04-02 CN CN202120682237.8U patent/CN214748697U/en active Active
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