CN113658728B - Test device for simulating dynamic scaling of secondary side of heat exchange tube of pressurized water reactor steam generator - Google Patents
Test device for simulating dynamic scaling of secondary side of heat exchange tube of pressurized water reactor steam generator Download PDFInfo
- Publication number
- CN113658728B CN113658728B CN202110870605.6A CN202110870605A CN113658728B CN 113658728 B CN113658728 B CN 113658728B CN 202110870605 A CN202110870605 A CN 202110870605A CN 113658728 B CN113658728 B CN 113658728B
- Authority
- CN
- China
- Prior art keywords
- heat exchange
- cylinder
- loop
- exchange tube
- tube
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/017—Inspection or maintenance of pipe-lines or tubes in nuclear installations
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a test device for simulating dynamic scaling of a secondary side of a heat exchange tube of a pressurized water reactor steam generator, which comprises a cylinder body; the tube bundle assembly is pushed into the cylinder from the first opening, a sliding assembly is arranged between the tube bundle assembly and the cylinder to enable the tube bundle assembly to be pushed into or moved out of the cylinder, the first baffle and the second baffle are arranged end to end, so that after the tube bundle assembly is placed into the cylinder, the first baffle seals the first opening and the second baffle seals the second opening, the cylinder is provided with a second loop inlet and a second loop outlet, and the second loop inlet and the second loop outlet are communicated with the cylinder to form a second heat exchange loop; and the first cylinder head and the second cylinder head are respectively detachably connected to the two ends of the cylinder body, the first cylinder head is provided with a first loop inlet, the second cylinder head is provided with a first loop outlet, and the first loop inlet and the first loop outlet are respectively communicated with the two ends of the heat exchange tube so as to form a first heat exchange loop. The invention is used for researching the scaling process of the heat exchange tube of the steam generator in the pressurized water reactor.
Description
Technical Field
The invention relates to the technical field of nuclear power, in particular to a test device for simulating dynamic scaling of a secondary side of a heat exchange tube of a pressurized water reactor steam generator.
Background
The steam generator in the nuclear power plant is a heat exchange device of a first loop and a second loop of the nuclear power plant, and mainly transfers heat in a coolant of the first loop to water of the second loop so as to generate steam and drive a steam turbine to generate electricity. The secondary loop equipment uses more carbon steel and low alloy steel materials, and forms Fe3O4 oxide with larger volume after being oxidized by water, and the formed oxide layer is peeled off and enters into the aqueous medium of the secondary loop to become sediment. These deposits gradually accumulate and adhere to the secondary side of the heat transfer tube through evaporation and concentration, forming a fouling layer. The heat transfer tube of the steam generator is a main device for realizing heat exchange, and if the surface of the heat transfer tube is scaled, the heat exchange efficiency of the steam generator is affected, and the service life of the heat transfer tube is endangered.
To ensure that the heat transfer tube meets the requirements, the heat transfer tube is required to be subjected to service performance tests including oxidation characteristics (corrosion resistance characteristics), which has an important guiding effect on promoting nuclear safety. To evaluate the oxidation characteristics of the heat transfer tube material, it is necessary to simulate the high temperature and high pressure environment of a pressurized water reactor steam generator. The corrosion occurs on the surface of the heat transfer tube material, the outer surface material is of a double-layer structure, the outer layer is loose and porous, the main component is NiFe2O4, and the corrosion product is deposited on the heat transfer tube; the inner layer is compact and is an oxide layer generated by the heat transfer pipe material and the secondary water. The dynamic scaling behavior of the heat transfer tube of the two-loop steam generator can be studied by detecting the deposition on the surface of the heat transfer tube.
During the shutdown of the nuclear power plant, video inspection is usually performed on areas such as a secondary side tube plate, and the related technology has limited inspection range, so that all heat transfer tube bundles and supporting structures cannot be inspected. Or eddy current inspection is used, but the method can only detect cracks on the surface and the inlet surface of the metal pipe. Chinese patent application (entitled "method for assessing heat exchanger fouling, publication No. CN111727352 a) which monitors the water level in a steam generator by means of a pressure sensor and only indicates the tendency and level of fouling by means of corresponding calculations, but cannot specifically detect and analyze the secondary side fouling composition of a heat transfer tube.
Disclosure of Invention
The present invention aims to solve, at least to some extent, one of the above technical problems in the prior art. Therefore, the embodiment of the invention provides a test device for simulating the dynamic scaling of the secondary side of the heat exchange tube of the pressurized water reactor steam generator, which is used for researching the scaling process of the heat exchange tube of the pressurized water reactor steam generator.
The test device for simulating dynamic scaling of the secondary side of the heat exchange tube of the pressurized water reactor steam generator comprises a cylinder body, wherein the head end of the cylinder body is provided with a first opening, and the tail end of the cylinder body is provided with a second opening; a tube bundle assembly pushed into the cylinder from the first opening, wherein a sliding assembly is arranged between the tube bundle assembly and the cylinder so as to enable the tube bundle assembly to be pushed into or moved out of the cylinder, the tube bundle assembly comprises a first baffle, a second baffle and a plurality of heat exchange tubes arranged between the first baffle and the second baffle, the first baffle and the second baffle are arranged end to end, so that after the tube bundle assembly is placed into the cylinder, the first baffle seals the first opening and the second baffle seals the second opening, the cylinder is provided with a second loop inlet and a second loop outlet, and the second loop inlet and the second loop outlet are communicated with the inside of the cylinder so as to form a second heat exchange loop; and the first cylinder head and the second cylinder head are respectively and detachably connected to the two ends of the cylinder body, the first cylinder head is provided with a first loop inlet, the second cylinder head is provided with a first loop outlet, and the first loop inlet and the first loop outlet are respectively communicated with the two ends of the heat exchange tube so as to form a first heat exchange loop.
In an alternative or preferred embodiment, the first baffle outer diameter is greater than the barrel inner diameter and the second baffle outer diameter is less than the barrel inner diameter.
In an alternative or preferred embodiment, the barrel has a radially inwardly extending flange at the second opening, and the second baffle is connected to the flange to close the second opening.
In an alternative or preferred embodiment, the second baffle is provided with a plurality of studs, and a first nut is connected after the studs pass through the flange so as to connect the second baffle with the flange.
In an alternative or preferred embodiment, the first barrel head screw is connected to the first opening of the barrel body, the second barrel head screw is connected to the second opening of the barrel body, and the first baffle plate is clamped between the first barrel head and the barrel body after the first barrel head is connected to close the first opening.
In an alternative or preferred embodiment, the sliding assembly comprises a slideway installed on the cylinder body and pulleys respectively arranged at two sides of the slideway, wherein the pulleys are installed on the tube bundle assembly, so that the tube bundle assembly slides along the slideway.
In an alternative or preferred embodiment, the tube bundle assembly further comprises at least one support plate between the first baffle and the second baffle, the heat exchange tubes passing through and being secured to the support plate, the pulleys being mounted on the support plate by pulley plates.
In an alternative or preferred embodiment, the middle part of the supporting plate is provided with a through hole for the heat exchange tube to pass through, and the through hole is a four-leaf hole.
In an alternative or preferred embodiment, the support plate comprises two support halves, a plurality of clamping block units are arranged between the two support halves and used for clamping the heat exchange tube, each clamping block unit comprises two mounting clamping blocks, through holes are formed after the two mounting clamping blocks are matched, and the two mounting clamping blocks are provided with connecting blocks for mounting first fasteners so that the two mounting clamping blocks clamp the heat exchange tube.
In an alternative or preferred embodiment, one of the support halves is fixed to the pulley plate and the other support half is bolted to the pulley plate, the pulley plate being provided with a spacer for bolting the support halves, the two mounting clips of the clip unit being mounted on opposite sides of the two support halves, respectively.
Based on the technical scheme, the embodiment of the invention has at least the following beneficial effects: according to the technical scheme, the first loop inlet, the heat exchange tube and the first loop outlet form a first heat exchange loop, the second loop inlet, the cylinder body and the second loop outlet form a second heat exchange loop, high-pressure water heated by the reactor core flows through the first heat exchange loop to exchange heat with cooling water of the second heat exchange loop, dynamic scale production is realized by introducing high-temperature high-pressure water, and a scale production mode of the heat exchange tube of the pressurized water reactor is simulated; by designing the sliding component, the tube bundle component can be pushed into or moved out of the cylinder, so that the tube bundle component can be stably fixed to a corresponding position, the integration degree of the tube bundle component is reserved, the tube bundle component can be moved out, and the scale formation study is carried out on heat exchange tubes of different materials; the whole device has higher separation degree, is convenient for cleaning and replacing, and has larger refitted space.
Drawings
The invention is further described below with reference to the drawings and examples;
FIG. 1 is a front view of an embodiment of the present invention;
FIG. 2 is a side view of an embodiment of the present invention;
FIG. 3 is a cross-sectional view taken along the direction A-A in FIG. 1;
FIG. 4 is a schematic view of the tube bundle assembly of an embodiment of the present invention;
FIG. 5 is an enlarged view of a portion of circle B of FIG. 1;
FIG. 6 is a partial view in the direction D of FIG. 5;
fig. 7 is a schematic view of the structure of a support plate in an embodiment of the present invention;
fig. 8 is a partial enlarged view of circle C in fig. 1.
Detailed Description
Reference will now be made in detail to the present embodiments of the present invention, examples of which are illustrated in the accompanying drawings, wherein the accompanying drawings are used to supplement the description of the written description so that one can intuitively and intuitively understand each technical feature and overall technical scheme of the present invention, but not to limit the scope of the present invention.
In the description of the present invention, it should be understood that references to orientation descriptions such as upper, lower, front, rear, left, right, etc. are based on the orientation or positional relationship shown in the drawings, are merely for convenience of description of the present invention and to simplify the description, and do not indicate or imply that the apparatus or elements referred to must have a particular orientation, be constructed and operated in a particular orientation, and thus should not be construed as limiting the present invention.
In the description of the present invention, a number means one or more, a number means two or more, and greater than, less than, exceeding, etc. are understood to not include the present number, and above, below, within, etc. are understood to include the present number. The description of the first and second is for the purpose of distinguishing between technical features only and should not be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated or implicitly indicating the precedence of the technical features indicated.
In the description of the present invention, unless explicitly defined otherwise, terms such as arrangement, installation, connection, etc. should be construed broadly and the specific meaning of the terms in the present invention can be reasonably determined by a person skilled in the art in combination with the specific contents of the technical scheme.
Referring to fig. 1-8, a test apparatus for simulating dynamic scaling of the secondary side of a heat exchange tube of a pressurized water reactor steam generator is shown and includes a cylinder 101, a tube bundle assembly 200, a first cylinder head 102, and a second cylinder head 103.
As shown in fig. 1 and 2, the tube 101 has a first opening at the head end and a second opening at the tail end, and the tube bundle assembly 200 is pushed into the interior of the tube 101 from the first opening, as shown in fig. 1.
The first barrel head 102 and the second barrel head 103 are detachably connected to two ends of the barrel 101 respectively, in this embodiment, the first barrel head 102 is connected to a first opening of the barrel 101 by a bolt, the second barrel head 103 is connected to a second opening of the barrel 101 by a bolt, and a specific bolt connection mode is that a flange is arranged for bolt connection. The first cylinder head 102 is provided with a first loop inlet 111, the second cylinder head 103 is provided with a first loop outlet 112, and the first loop inlet 111 and the first loop outlet 112 are respectively communicated with two ends of the heat exchange tube 201 to form a first heat exchange loop.
A sliding component 240 is arranged between the tube bundle assembly 200 and the inside of the cylinder body so as to realize that the tube bundle assembly 200 can be pushed into or removed from the cylinder body 101, the tube bundle assembly 200 comprises a first baffle 211, a second baffle 212 and a plurality of heat exchange tubes 201 arranged between the first baffle 211 and the second baffle 212, the first baffle 211 and the second baffle 212 are arranged in an end-to-end mode, after the tube bundle assembly 200 is placed in the cylinder body 101, the first baffle 211 closes the first opening and the second baffle 212 closes the second opening, the cylinder body 101 is provided with a second loop inlet 121 and a second loop outlet 122, and the second loop inlet 121 and the second loop outlet 122 are communicated with the inside of the cylinder body 101 so as to form a second heat exchange loop. In this embodiment, the tube bundle assembly 200 is provided with three heat exchange tubes in total, which are arranged in parallel one above the other.
It can be understood that the high-pressure water heated by the reactor core flows through the first heat exchange loop to exchange heat with the cooling water of the second heat exchange loop, and the dynamic scale generation is realized by adopting a mode of introducing the high-temperature high-pressure water, so that the scale generation mode of the heat exchange tube of the pressurized water reactor steam generator is simulated. In this embodiment, by designing the sliding component 240, the tube bundle component 200 can be pushed into or removed from the cylinder 101, so that the tube bundle component 200 can be stably fixed at a corresponding position, the integration degree of the tube bundle component 200 is maintained, the tube bundle component 200 can be removed, and the scale formation study can be performed on heat exchange tubes of different materials. The test device for simulating dynamic scaling of the secondary side of the heat exchange tube of the pressurized water reactor steam generator has higher separation degree of the whole device, and the whole device is convenient to clean and replace after the tube bundle assembly is moved out, thereby providing convenience for detecting corrosion scaling products of the heat transfer tube and greatly improving the working efficiency.
In addition, the first cylinder head 102 and the second cylinder head 103 are double-layer cavities, so that heat loss of the first heat exchange loop can be reduced, and two sections of arc-shaped electric heating rods 106 are arranged inside the first cylinder head 102 and the second cylinder head 103, so that water in the first heat exchange loop can be heated and insulated, heat loss generated by the water and the outside can be compensated, and heat transfer between the water and water in the second heat exchange loop can be fully realized.
In the test device for simulating dynamic scaling of the secondary side of the heat exchange tube of the pressurized water reactor steam generator, the tube bundle assembly 200 adopts the sliding assembly 240 to push in or move out of the cylinder 101, so that the assembly, the disassembly and the cleaning are convenient. Specifically, as shown in fig. 5 and 6, the sliding assembly 240 includes a slideway 241 installed on the cylinder 101 and pulleys 242 separately provided at both sides of the slideway 241, and the pulleys 242 are installed on the tube bundle assembly 200, thereby realizing sliding of the tube bundle assembly 200 along the slideway 241.
In addition, as shown in fig. 3, 4 and 7, in one embodiment, the tube bundle assembly 200 further includes at least one support plate 220 between the first baffle 211 and the second baffle 212, and in this embodiment, three support plates 220 are provided in total, the heat exchange tube 201 passes through the support plates 220 and is fixed to the support plates 220, and the pulley 242 is mounted on the support plates 220 by means of pulley plates 231. Further, the middle part of the supporting plate 220 is provided with a through hole 223 for the heat exchange tube 201 to pass through, and the through hole is a four-leaf hole, it can be understood that the four-leaf hole can reduce the contact area between the supporting plate 220 and the heat exchange tube 201, that is, the supporting plate 220 with the four-leaf hole is designed to fix the heat exchange tube 201, so that the structural stability of the heat exchange tube 201 is ensured, meanwhile, the contact area of the four-leaf hole can be reduced by nearly 70% compared with the round hole, and the heat exchange effect of the heat exchange tube can be effectively improved.
In this embodiment, the cylinder 101 is horizontal, and the supporting seats 104 on the left and right sides below the cylinder 101 play a supporting role. The first loop inlet 111 is arranged at the left end of the first cylinder head 102 and the first loop outlet 112 is arranged at the right end of the second cylinder head 103, and the first loop inlet 111 and the first loop outlet 112 are both provided with a flow rate transmitter and a pipeline thermometer for detecting the flow rate and the temperature of water in the first heat exchange loop. In a normal working state, the heated water of the first heat exchange loop enters the cavity of the first cylinder head 101 through the first loop inlet 111, enters the heat exchange tube 201, and finally flows out from the first loop outlet 112 to form the first heat exchange loop. The cooling water flows in from the second circuit inlet 121, exchanges heat with the water in the first heat exchange circuit in the cylinder 101, and generates steam, which is discharged from the second circuit outlet 122, and the second circuit outlet 122 is a steam outlet. Preferably, the bottom of the cylinder 101 is also provided with a liquid outlet 127 for discharging waste liquid generated during the test.
The top of the cylinder 101 is provided with various nozzles which are separated from each other, as shown in fig. 1, from left to right, a pressure gauge nozzle 123, a second loop inlet 121, a gas state thermo-meter nozzle 125 positioned in the second loop outlet 122, and a safety valve port 124, and in addition, the middle position of the cylinder 101 is provided with a liquid state thermo-meter nozzle 126. The pressure gauge pipe orifice 123 is used for installing a pressure gauge, and the gas thermometer pipe orifice 125 and the liquid thermometer pipe orifice 126 are used for a thermometer so as to detect the pressure in the device, the temperature of water of the second heat exchange circuit and the steam temperature.
In this embodiment, the outer diameter of the first baffle 211 is larger than the inner diameter of the cylinder 101, the outer diameter of the second baffle 212 is smaller than the inner diameter of the cylinder 101, and the tube bundle assembly 200 can be pushed into the cylinder 101 smoothly. In one aspect, the barrel 101 has a radially inwardly extending flange 105 at the second opening, and a second baffle 212 is coupled to the flange 105 to close the second opening; further, as shown in fig. 8, the second baffle 212 is provided with a plurality of studs 251, and the studs 251 pass through the flange 105 and are connected with a first nut 252 so as to connect the second baffle 212 with the flange 105. On the other hand, after the first cylinder head 102 is connected with the cylinder 101, the first baffle 211 is clamped between the first cylinder head and the cylinder 101 to close the first opening, and sealing gaskets are arranged on two sides of the first baffle 211. After the tube bundle assembly 200 is pushed into the cylinder 101, the liquid of the first heat exchange loop is effectively prevented from being in direct contact with the liquid of the second heat exchange loop, meanwhile, the high-degree detachability of the device is realized, and the observation and research on the heat transfer tube after scaling are facilitated.
As shown in fig. 3, 4 and 7, the support plate 220 includes two support halves 221, a plurality of clamping block units are disposed between the two support halves 221 for clamping the heat exchange tube 201, each clamping block unit includes two mounting clamping blocks 222, through holes 223 are formed after the two mounting clamping blocks 222 are matched, and the two mounting clamping blocks 222 are provided with connecting blocks 224 for mounting first fasteners 225, so that the two mounting clamping blocks 222 clamp the heat exchange tube 201. The two mounting clips 222 of the clip unit are mounted on opposite sides of the two support halves 221, respectively. In this embodiment, two mounting clips 222 of a portion of the clip unit employ a connection block 224.
During installation, the heat exchange tube 201 is firstly placed into the installation clamping blocks 222 of the support half body 221 when in use, then the other corresponding support half body 221 is installed, the two corresponding installation clamping blocks 222 are matched, and then the connection blocks 224 on the installation clamping blocks 222 are connected by adopting the first fastening pieces 225, so that the heat exchange tube 201 is clamped. The support plate 220 with four-leaf holes is used for fixing the heat exchange tube 201, so that the structural stability of the heat exchange tube 201 is ensured, meanwhile, the contact area of the four-leaf holes compared with the round holes can be reduced by nearly 70%, and the heat exchange effect of the heat exchange tube can be effectively improved. Meanwhile, one of the supporting halves 221 is fixed on the pulley plate 231, the other supporting half 221 is bolted on the pulley plate 231, the pulley plate 231 is provided with a positioning piece 226 to which the supporting half 221 is bolted, and the supporting half 221 is connected with the positioning piece 226 by a second fastener 227. The first fastener 225 and the second fastener 227 each employ a fastener in the form of a bolt and nut.
The process of the test device for simulating the dynamic scaling of the secondary side of the heat exchange tube of the pressurized water reactor steam generator comprises the following steps: connecting an external pipeline for conveying high-temperature and high-pressure water with the first loop inlet 111, wherein a flow rate transmitter is provided with a flow rate transmitter and a pipeline thermometer, so that the high-temperature and high-pressure water enters the cavity of the first barrel head 102; high-temperature and high-pressure water continuously accumulates in the cavity of the first cylinder head 102, enters the heat exchange tube 201, flows through the heat exchange tube 201, flows out of the first loop outlet 112, and flows out of the first loop outlet, and is provided with a flow rate transmitter and a pipeline thermometer. The coolant of the second heat exchange circuit enters the cylinder 101 from the second circuit inlet 121, exchanges heat with the heat exchange tube 201, and the generated steam exits the cylinder 101 from the second circuit outlet 122.
The process of heat exchange between the water in the first heat exchange loop and the cooling water in the second heat exchange loop is the process of simulating dynamic scaling of the heat exchange tube. In the reaction process, the temperature of the water inlet and outlet of the first heat exchange loop, the liquid temperature and the steam temperature of the second heat exchange loop and the pressure in the cylinder body in the device are monitored in real time through a thermometer, a pressure gauge, a pipeline thermometer and a flow rate transmitter, so as to detect the dynamic scale-producing environment of the heat exchange tube.
After the reaction is completed, the introduction of high-temperature and high-pressure water into the first heat exchange circuit is stopped, and the waste liquid and residues generated in the process are discharged through the liquid discharge port 127. The tube bundle assembly 200 can be integrally slid out of the tube 101 through the pulley 242 by removing the bolts connecting and fixing the tube 101 with the first tube head 102 and the second tube head 103 at both sides to separate them and removing the first nuts 252 on the studs 251 of the second baffle. And then removing the first fastening piece 225 of the connecting block 224 on the mounting clamp block 222 and removing the second fastening piece 227 connected with the supporting half body 221 and the positioning piece 226, and taking out the heat exchange tube 201 to detect and study the scale formation component on the heat exchange tube.
The test device for simulating dynamic scaling on the secondary side of the heat exchange tube of the pressurized water reactor steam generator has high separation degree, and the combination of the pulley and the slideway enables the heat exchange tube to be installed and disassembled conveniently and rapidly, so that the modification space is large.
The embodiments of the present invention have been described in detail with reference to the accompanying drawings, but the present invention is not limited to the above embodiments, and various changes can be made within the knowledge of one of ordinary skill in the art without departing from the spirit of the present invention.
Claims (8)
1. Test device of simulation pressurized water reactor steam generator heat exchange tube secondary side developments scale deposit, its characterized in that: comprising
The device comprises a barrel body (101), wherein the head end of the barrel body (101) is provided with a first opening, and the tail end of the barrel body is provided with a second opening;
a tube bundle assembly (200) pushed into the cylinder (101) from the first opening, a sliding assembly (240) is arranged between the tube bundle assembly (200) and the cylinder so as to enable the tube bundle assembly (200) to be pushed into or moved out of the cylinder (101), the sliding assembly (240) comprises a slideway (241) installed on the cylinder (101) and pulleys (242) arranged on two sides of the slideway (241), the pulleys (242) are installed on the tube bundle assembly (200) so as to enable the tube bundle assembly (200) to slide along the slideway (241), the tube bundle assembly (200) comprises a first baffle plate (211), a second baffle plate (212) and a plurality of heat exchange tubes (201) arranged between the first baffle plate (211) and the second baffle plate (212), the first baffle plate (211) and the second baffle plate (212) are arranged in an end-to-end mode so that after the tube bundle assembly (200) is placed into the cylinder (101), the first baffle plate (211) and the second opening (212) are sealed, the second baffle plate (200) is further arranged between the first baffle plate (211) and the second baffle plate (212) and the second baffle plate (200) are sealed, the heat exchange tube (201) penetrates through the supporting plate (220) and is fixed with the supporting plate (220), the pulley (242) is installed on the supporting plate (220) through a pulley plate (231), the cylinder (101) is provided with a second loop inlet (121) and a second loop outlet (122), and the second loop inlet (121) and the second loop outlet (122) are communicated with the inside of the cylinder (101) to form a second heat exchange loop; and
the first cylinder head (102) and the second cylinder head (103) which are respectively and detachably connected with the two ends of the cylinder body (101), the first cylinder head (102) is provided with a first loop inlet (111), the second cylinder head (103) is provided with a first loop outlet (112), and the first loop inlet (111) and the first loop outlet (112) are respectively communicated with the two ends of the heat exchange tube (201) to form a first heat exchange loop.
2. The test device for simulating dynamic scaling of the secondary side of a heat exchange tube of a pressurized water reactor steam generator according to claim 1, wherein: the outer diameter of the first baffle plate (211) is larger than the inner diameter of the cylinder body (101), and the outer diameter of the second baffle plate (212) is smaller than the inner diameter of the cylinder body (101).
3. The test device for simulating dynamic scaling of the secondary side of a heat exchange tube of a pressurized water reactor steam generator according to claim 2, wherein: the cylinder (101) has a radially inwardly extending flange (105) at a second opening, and the second baffle (212) is connected to the flange (105) to close the second opening.
4. A test device for simulating dynamic scaling of the secondary side of a heat exchange tube of a pressurized water reactor steam generator according to claim 3, wherein: the second baffle (212) is provided with a plurality of studs (251), and the studs (251) penetrate through the flange (105) and are connected with first nuts (252) so as to enable the second baffle (212) to be connected with the flange (105).
5. The test device for simulating dynamic scaling of the secondary side of a heat exchange tube of a pressurized water reactor steam generator according to claim 2, wherein: the first cylinder head (102) is connected to a first opening of the cylinder body (101) through a bolt, the second cylinder head (103) is connected to a second opening of the cylinder body (101) through a bolt, and the first baffle (211) is clamped between the first cylinder head (102) and the cylinder body (101) after the first cylinder head (102) is connected to the cylinder body to close the first opening.
6. The test device for simulating dynamic scaling of the secondary side of a heat exchange tube of a pressurized water reactor steam generator according to claim 1, wherein: the middle part of the supporting plate (220) is provided with a through hole (223) for the heat exchange tube (201) to pass through, and the through hole is a four-leaf hole.
7. The test device for simulating dynamic scaling of the secondary side of a heat exchange tube of a pressurized water reactor steam generator of claim 6, wherein: the support plate (220) comprises two support half bodies (221), a plurality of clamping block units are arranged between the two support half bodies (221) and used for clamping the heat exchange tube (201), each clamping block unit comprises two installation clamping blocks (222), through holes (223) are formed after the two installation clamping blocks (222) are matched, and connecting blocks (224) for installing first fasteners (225) are arranged on the two installation clamping blocks (222) so that the two installation clamping blocks (222) clamp the heat exchange tube (201).
8. The test device for simulating dynamic scaling of the secondary side of a heat exchange tube of a pressurized water reactor steam generator of claim 7, wherein: one of the supporting half bodies (221) is fixed on the pulley plate (231), the other supporting half body (221) is connected to the pulley plate (231) through bolts, the pulley plate (231) is provided with a locating plate (226) for the supporting half body (221) to be connected through bolts, and two mounting clamping blocks (222) of the clamping block unit are respectively mounted on opposite sides of the two supporting half bodies (221).
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110870605.6A CN113658728B (en) | 2021-07-30 | 2021-07-30 | Test device for simulating dynamic scaling of secondary side of heat exchange tube of pressurized water reactor steam generator |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202110870605.6A CN113658728B (en) | 2021-07-30 | 2021-07-30 | Test device for simulating dynamic scaling of secondary side of heat exchange tube of pressurized water reactor steam generator |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN113658728A CN113658728A (en) | 2021-11-16 |
| CN113658728B true CN113658728B (en) | 2023-08-15 |
Family
ID=78490141
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202110870605.6A Active CN113658728B (en) | 2021-07-30 | 2021-07-30 | Test device for simulating dynamic scaling of secondary side of heat exchange tube of pressurized water reactor steam generator |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN113658728B (en) |
Families Citing this family (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN114279734A (en) * | 2021-12-23 | 2022-04-05 | 苏州热工研究院有限公司 | Pipe scale generation simulation device and pipe scale generation simulation method |
| CN115440401A (en) * | 2022-08-16 | 2022-12-06 | 核动力运行研究所 | Lead bismuth pile direct current steam generator |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101290190A (en) * | 2008-01-25 | 2008-10-22 | 钱建荣 | Cement rotary kiln barrel radiation, reclaiming and utilizing device |
| CN103545000A (en) * | 2013-10-21 | 2014-01-29 | 中国核动力研究设计院 | Secondary-side passive residual heat discharging heat exchanger simulation device and method |
| CN104071477A (en) * | 2014-06-24 | 2014-10-01 | 浙江久立特材科技股份有限公司 | Packaging method and packaging box of heat transfer pipes for nuclear steam generator |
| CN107143833A (en) * | 2017-05-05 | 2017-09-08 | 中广核研究院有限公司 | Multiple-unit tubular type once through steam generator |
| CN110953562A (en) * | 2019-12-10 | 2020-04-03 | 苏州热工研究院有限公司 | Vertical natural circulation steam generator |
| CN113096840A (en) * | 2021-03-29 | 2021-07-09 | 中山大学 | Reaction kettle for simulating dynamic test of reactor fuel rod cladding material |
-
2021
- 2021-07-30 CN CN202110870605.6A patent/CN113658728B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101290190A (en) * | 2008-01-25 | 2008-10-22 | 钱建荣 | Cement rotary kiln barrel radiation, reclaiming and utilizing device |
| CN103545000A (en) * | 2013-10-21 | 2014-01-29 | 中国核动力研究设计院 | Secondary-side passive residual heat discharging heat exchanger simulation device and method |
| CN104071477A (en) * | 2014-06-24 | 2014-10-01 | 浙江久立特材科技股份有限公司 | Packaging method and packaging box of heat transfer pipes for nuclear steam generator |
| CN107143833A (en) * | 2017-05-05 | 2017-09-08 | 中广核研究院有限公司 | Multiple-unit tubular type once through steam generator |
| CN110953562A (en) * | 2019-12-10 | 2020-04-03 | 苏州热工研究院有限公司 | Vertical natural circulation steam generator |
| CN113096840A (en) * | 2021-03-29 | 2021-07-09 | 中山大学 | Reaction kettle for simulating dynamic test of reactor fuel rod cladding material |
Also Published As
| Publication number | Publication date |
|---|---|
| CN113658728A (en) | 2021-11-16 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN113658728B (en) | Test device for simulating dynamic scaling of secondary side of heat exchange tube of pressurized water reactor steam generator | |
| TWI593934B (en) | Modular plate and shell heat exchanger | |
| KR20120007018A (en) | Modular plate and shell heat exchanger | |
| CN110763617A (en) | Test device for complex atmosphere corrosion coupling high-temperature solid-phase erosion corrosion | |
| CN107830750B (en) | Ash cooler for coal gasification furnace | |
| CN101694432B (en) | Method for evaluating reliability of thermal barrier coating system and device thereof | |
| CN104568716A (en) | Clean-type corrosion monitoring coupon device and clean-type corrosion monitoring method | |
| CN104949550A (en) | Casing pipe floating type evaporation and vaporization device | |
| CN113096840B (en) | Reaction kettle for simulating dynamic test of reactor fuel rod cladding material | |
| CN2672595Y (en) | Inclined baffle table still heat exchanger | |
| CN106769814B (en) | Low-temperature corrosion detection system and detection method thereof | |
| CN113959700B (en) | Device and method for testing performance of cooling liquid jet flow equally-dividing component of multi-strand grouping jet flow | |
| CN112903275B (en) | Sectional type pull rod sealing system for thermal engine coupling fatigue test of blade | |
| CN203630019U (en) | Cleaning type corrosion monitoring bracket device | |
| CN111578749A (en) | Floating heat exchanger | |
| CN103017337B (en) | High-frequency induction fluid heater | |
| CN212538908U (en) | Floating heat exchanger | |
| CN101526318A (en) | Thin-tube-plate segment anodic protection stainless steel shell-and-tube concentrated sulfuric acid cooling tower | |
| CN109631621B (en) | Heat exchanger suitable for purifying high-purity medium and preparation method thereof | |
| CN215984039U (en) | Split closed type condenser for silicone sealant | |
| CN212109658U (en) | Dividing wall type heat exchanger structure for heat exchange | |
| CN215725405U (en) | Pipe box of non-screwed plug type air cooler and non-screwed plug type air cooler | |
| CN204730706U (en) | The floating type carburation by evaporation device of sleeve pipe | |
| CN220893081U (en) | Waste heat recovery device | |
| CN215491213U (en) | Tube type heat exchanger capable of improving heat exchange efficiency |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |