CN110828010A - Reactor core assembly sub-channel flow measurement test device and method - Google Patents
Reactor core assembly sub-channel flow measurement test device and method Download PDFInfo
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Abstract
A device and a method for measuring flow of a reactor core assembly sub-channel comprise a lower cavity, a rectifier, a positioning piece, a rod bundle sleeve, a rod bundle test piece, a fixing frame, a visualization section, an upper cavity, a corrugated pipe, a rotary joint, a moving device and a sampling probe. The rectifier is arranged at the upper part of the lower cavity and is used for shortening the length of the straight pipe section and reducing the influence of the rotational flow of the inlet cavity; the positioning piece is positioned at the bottom of the rod bundle sleeve and used for fixing the position of the rod bundle test piece; the visualization section is positioned at the top end of the rod bundle sleeve, so that the position of the sampling probe can be conveniently aligned; the rotary joint is arranged at the top end of the corrugated pipe, the sampling probe is fixed on the rotary joint through a bolt, and the sampling probe is used for realizing extraction and measurement of the flow of the sub-channel; the mobile device can realize the adjustment of the position and the angle of the sampling probe and is used for the online measurement of the flow of each subchannel at the outlet of the component; the whole device is fixedly connected through a fixing frame; the device can realize the measurement of the outlet flow of the subchannel of various types of components.
Description
Technical Field
The invention belongs to the field of rod bundle flow characteristic tests, and particularly relates to a reactor core assembly sub-channel flow measurement test device and method.
Background
The reactor core is composed of a plurality of component flow channels with different thermal powers and different flow resistance coefficients, such as fuel components, control rod components, breeder zone components, reflector layer components, shield zone components and the like, and the flow distribution in the channels is different. With the development of reactor technology and the development of various large power station projects in China, the development of reactor sub-channel programs with independent intellectual property rights is particularly important, and the development of reactor core safety analysis can provide important theoretical support for core safety design. However, the development of the above procedure requires a series of accurate and reliable auxiliary model supports, such as a heat exchange model, a resistance coefficient model, a mixing model and the like of the coolant.
The bundle channel is the type of channel closest to the actual conditions within the stack, and since the study of a single rod or bundle as a whole cannot take into account the differences between channels, it is necessary to study the bundle sub-channels in order to more truly simulate the in-stack flow process. With the progress of experimental conditions in recent years, the improvement of the subchannel model and the rapid improvement of the computer computing capability make experimental and theoretical analysis of the rod bundle possible. The invention is based on the invention and provides the reactor core assembly sub-channel flow measurement test device and the method thereof, which can provide reference for development of sub-channel level auxiliary models and verification of programs.
The existing assembly sub-channel flow measurement test technology still has some defects, such as the sub-channel isolation pore plate is arranged at the outlet of the assembly to separate the flow of the sub-channel, and the flow distribution of the sub-channel at the outlet of the assembly is disturbed to a certain extent; if the sampling visualization section at the outlet of the component adopts a circular tube structure, sudden expansion is formed at the outlet of the component, and the flow measurement of the outlet sub-channel is seriously influenced; if no rectifying piece is placed, the flow distribution is not fully developed, and experimental errors are caused; such as laser particle imaging, the test apparatus is expensive to manufacture, the method is more sophisticated for local phenomenon simulation but still has some error in the subchannel outlet flow statistics, and the processing requirements are too high for complex structural components such as tape-wound component test pieces.
Disclosure of Invention
In order to solve the problems in the prior art, the invention provides a reactor core assembly sub-channel flow measurement test device and a method, the test device is suitable for various types of assemblies, can conveniently and effectively obtain the flow distribution condition of each sub-channel of the assembly, and can be used for not only mechanism model development but also provide reference for design and program verification of various types of assemblies.
In order to achieve the purpose, the invention adopts the following technical scheme:
a flow measurement test device for a reactor core assembly sub-channel comprises a rod bundle test piece 5 for simulating the reactor core assembly sub-channel, wherein the rod bundle test piece 5 is arranged in a rod bundle sleeve 4 and is fixed through a positioning piece 3 at the bottom end of the rod bundle sleeve 4; the rectifier 2 is positioned below the rod bundle sleeve 4, the lower cavity 1 is positioned at the lower part of the rectifier 2, and the rectifier 2 is used for straightening an inlet flow field; the visualization section 7 is arranged at the top of the rod bundle sleeve 4, and the top end of the rod bundle test piece 5 is positioned in the middle of the visualization section 7 and is connected with the bottom of the sampling probe 12, so that whether the sampling probe 12 is aligned with a sub-channel to be tested or not can be observed conveniently; the upper chamber 8 is positioned at the top of the visualization section 7 and used for returning water to a main loop; the top of the upper chamber 8 is connected with a corrugated pipe 9, and a rotary joint 10 is arranged in the center of a flange at the top of the corrugated pipe 9 and is connected with a worm gear mechanism arranged in the Z-axis direction of a moving device 11 to realize the rotation of a sampling probe 12; the sampling probe 12 is inserted into the rotary joint 10 and is fixedly connected through a small flange at the top of the rotary joint 10; a flange at the top of the corrugated pipe 9 is fixedly connected with a grabbing head at the lower end of a Z shaft of the moving device 11, so that the sampling probe 12 can move in the three-dimensional direction; the rod bundle sleeve 4 is connected with the fixing frame 6 to realize the fixation of the test device; the lower chamber 1 inlet line and the upper chamber 8 outlet line are connected to the entire test loop.
The visualization section 7 is made of transparent materials, the material performance meets the requirement of test working conditions, the rod bundle test piece 5 is divided into an upper section and a lower section which are identical in geometric shape but different in flow section size by taking the height of the top end as a boundary, the geometric dimension of the section of the lower section is completely identical to that of the rod bundle casing 4, the geometric dimension of the section of the upper section is larger than that of the lower section, the inner wall surface of the upper section is widened outwards by 1mm, the wall surface thickness of a sampling flow channel of the sampling probe 12 is considered, space is reserved for the sampling probe 12 of the side and corner sub-channel by widening the design of the flow section, and the sampling probe 12 of the side and corner sub-channel can be aligned with.
The top end of the rod bundle test piece 5 is of a concave conical structure, the bottom end of the sampling probe 12 is of a convex conical structure with the same geometry, and the two conical structures can be in butt joint in a matched mode, so that the sampling probe 12 can be aligned with a sub-channel to be tested.
The moving device 11 has four degrees of freedom, can realize the movement of any direction of a three-dimensional space and the adjustment of any angle of a horizontal plane, comprises an X shaft, a Y shaft and a Z shaft, realizes the translation through a screw rod device, is provided with a worm gear mechanism in the Z shaft direction to realize the angle adjustment of the sampling probe 12 in the X-Y plane, can be manually or mechanically operated in the adjusting process, and has higher adjusting precision in the whole set of moving device 11.
The rod bundle test piece 5 is fixed by the positioning piece 3 at the bottom of the rod bundle casing 4 in a bottom fixing mode, and the outlet at the top end of the rod bundle test piece 5 is not restricted due to the fact that the flow of the opening channel needs to be measured; according to actual conditions, the middle part of the rod bundle test piece 5 can be fixed by adding the positioning piece 3 according to different component types.
And a hole is formed in the side surface of the flange at the top of the corrugated pipe 9, a valve is welded, and high-point exhaust is realized at the test starting stage.
The sampling probe 12 comprises a plurality of groups of pressure measuring pipes for measuring the static pressure of the sub-channel to be measured at the outlet of the rod bundle test piece 5 and the adjacent sub-channels thereof.
In the test method of the reactor core assembly sub-channel flow measurement test device, in the test loop starting stage, a main loop pump is started, test working media are pumped into the test device, and a vent valve of a corrugated pipe 9 is opened until loop gas is exhausted; when no bubble exists in the visualization section 7, a plurality of groups of pressure measuring pipes in the sampling probe 12 are exhausted and connected with a differential pressure transmitter; after the exhaust work is finished, the mobile device 11 is used for finishing the adjustment of the position and the angle of the sampling probe 12, and the visual section 7 is observed to ensure that the sampling probe 12 is in butt joint with the sub-channel to be detected; controlling the flow extracted by the sampling probe 12 by adjusting the opening of a valve connected with an outlet pipe of the sampling probe 12 to ensure that the static pressure of the sub-channel to be measured is the same as the average static pressure of all adjacent external sub-channels, wherein the flow extracted by the sampling probe 12 is the real flow of the sub-channel to be measured, and recording the flow meter data on the outlet pipeline of the sampling probe 12 by a data acquisition system to complete the flow measurement of the sub-channel to be measured; then, the flow of the sub-channel at other positions is measured through the moving device 11, and when the angle of the next sub-channel to be measured and the angle of the previous sub-channel are changed, the angle of the sampling probe 12 is adjusted through a worm gear mechanism of the moving device 11.
Compared with the prior art, the invention has the following advantages:
1. the moving device is designed and built on the basis of the lead screw, the worm gear mechanism and the rotary joint, can realize the adjustment of any angle and any sub-channel position of the sampling probe, is convenient and quick to replace the sampling probe, has the characteristics of high precision, automation and the like, and can more accurately position the sampling probe.
2. The geometry of the visualization section is determined by the geometry of the rod bundle casing, the geometry of the lower half section is completely consistent with that of the rod bundle casing, the upper half section is slightly wider than the lower half section by 1mm, the length of the outlet section is prolonged by the design of the visualization section, the outlet effect of a flow field is reduced, and the reasonability of flow distribution of the outlet sub-channel is ensured on the premise that the side and corner sampling probes can be inserted and aligned.
3. The rectifier and the inlet and outlet pipelines of the upper and lower chambers which are symmetrically arranged are easy to eliminate the influence caused by the inlet and outlet effect and the rotating flow, reduce the lengths of the rod bundle test piece and the inlet straight pipe section, enable the fluid to be developed more quickly and fully, and save the processing cost while ensuring the test precision.
4. The sampling device and the rod bundle adopt a conical matching mode, so that the positioning of the sampling probe is convenient, the problem that the sampling probe cannot be aligned due to the deviation of the geometric dimension and the ideal dimension of the outlet of the rod bundle caused by machining errors and the like is solved, and the measuring precision of the flow of the sub-channel is improved.
5. The sub-channel flow measurement test device and the method have strong applicability, can be used for various flow working conditions and cover any flow pattern; flow distribution tests can be carried out for various types of components; the flow distribution measurement under different working conditions, such as the flow blockage working condition, can be realized. The whole design is simple and practical, the construction cost is low, and tools and means are provided for the research of the flow heat exchange mechanism at the subchannel level.
Drawings
FIG. 1 is a schematic diagram of the overall structure of a reactor core assembly sub-channel flow measurement test device according to the present invention;
as shown in fig. 1, 1 is a lower chamber, 2 is a rectifier, 3 is a positioning member, 4 is a rod bundle casing, 5 is a rod bundle test piece, 6 is a fixing frame, 7 is a visualization section, 8 is an upper chamber, 9 is a corrugated pipe, 10 is a rotary joint, 11 is a moving device, and 12 is a sampling probe.
Fig. 2 is a schematic cross-sectional view of three types of rod bundle test pieces aimed at by the reactor core assembly subchannel flow measurement test device of the present invention, wherein fig. 2a is a square rod bundle test piece including three types of subchannels, i.e., inner, side and corner, fig. 2b is a hexagonal rod bundle test piece including three types of subchannels, i.e., inner, side and corner, and fig. 2c is a circular rod bundle test piece including two types of inner subchannels and one type of side subchannels.
FIG. 3 is a schematic structural diagram of a mobile device in a reactor core assembly sub-channel flow measurement test device according to the present invention;
as shown in fig. 3, 111 is a worm gear mechanism, 10 is a rotary joint, 113 is a gripper, 114 is a Z-axis, 115 is a hand wheel, 116 is a lead screw, 117 is an X-axis, and 118 is a Y-axis.
Detailed Description
The invention is described in detail below with reference to the following figures and detailed description:
as shown in figure 1, the invention relates to a reactor core assembly subchannel flow measurement test device, which comprises a lower chamber 1, a rectifier 2, a positioning piece 3, a rod bundle sleeve 4, a rod bundle test piece 5, a fixed frame 6, a visualization section 7, an upper chamber 8, a corrugated pipe 9, a rotary joint 10, a moving device 11 and a sampling probe 12.
The rod bundle test piece 5 is arranged in the rod bundle casing 4 and is fixed through the positioning piece 3 at the bottom end of the rod bundle casing 4; the rectifier 2 is positioned below the rod bundle sleeve 4, the lower cavity 1 is positioned at the lower part of the rectifier 2, and the rectifier 2 is used for straightening an inlet flow field; the visualization section 7 is arranged at the top of the rod bundle sleeve 4, and the top end of the rod bundle test piece 5 is positioned in the middle of the visualization section 7 and is connected with the bottom of the sampling probe 12, so that whether the sampling probe 12 is aligned with a sub-channel to be tested or not can be observed conveniently; the upper chamber 8 is positioned at the top of the visualization section 7 and used for returning water to a main loop; the top of the upper chamber 8 is connected with a corrugated pipe 9, and a rotary joint 10 is arranged in the center of a flange at the top of the corrugated pipe 9 and is connected with a worm gear mechanism arranged in the Z-axis direction of a moving device 11 to realize the rotation of a sampling probe 12; the sampling probe 12 is inserted into the rotary joint 10 and is fixedly connected through a small flange at the top of the rotary joint; a flange at the top of the corrugated pipe 9 is fixedly connected with a grabbing head at the lower end of a Z shaft of the moving device 11, so that the sampling probe 12 can move in the three-dimensional direction; the rod bundle sleeve 4 is connected with the fixing frame 6 to realize the fixation of the test device; the lower chamber 1 inlet line and the upper chamber 8 outlet line are connected to the entire test loop.
The visualization section 7 is made of transparent materials, the material performance meets the requirement of test working conditions, the rod bundle test piece 5 is divided into an upper section and a lower section which are identical in geometric shape but different in flow section size by taking the height of the top end as a boundary, the geometric dimension of the section of the lower section is completely identical to that of the rod bundle casing 4, the geometric dimension of the section of the upper section is larger than that of the lower section, the inner wall surface of the upper section is widened outwards by 1mm, the wall surface thickness of a sampling flow channel of the sampling probe 12 is considered, space is reserved for the sampling probe 12 of the side and corner sub-channel by widening the design of the flow section, and the sampling probe 12 of the side and corner sub-channel can be aligned with.
The top end of the rod bundle test piece 5 is of a concave conical structure, the bottom end of the sampling probe 12 is of a convex conical structure with the same geometry, and the two conical structures can be in butt joint in a matched mode, so that the sampling probe 12 can be aligned with a sub-channel to be tested.
The moving device 11 has four degrees of freedom, can realize the movement of any direction of a three-dimensional space and the adjustment of any angle of a horizontal plane, comprises an X shaft, a Y shaft and a Z shaft, realizes the translation through a screw rod device, is provided with a worm gear mechanism in the Z shaft direction to realize the angle adjustment of the sampling probe 12 in the X-Y plane, can be manually or mechanically operated in the adjusting process, and has higher adjusting precision in the whole set of moving device 11.
The rod bundle test piece 5 is fixed by the positioning piece 3 at the bottom of the rod bundle casing 4 in a bottom fixing mode, and the outlet at the top end of the rod bundle test piece 5 is not restricted due to the fact that the flow of the opening channel needs to be measured; according to actual conditions, the middle part of the rod bundle test piece 5 can be fixed by adding the positioning piece 3 according to different component types.
And a hole is formed in the side surface of the flange at the top of the corrugated pipe 9, a valve is welded, and high-point exhaust is realized at the test starting stage.
The sampling probe 12 comprises a plurality of groups of pressure measuring pipes for measuring the static pressure of the sub-channel to be measured at the outlet of the rod bundle test piece 5 and the adjacent sub-channels thereof.
As shown in fig. 2a, 2b and 2c of fig. 2, a reactor core assembly sub-channel flow measurement test apparatus of the present invention is suitable for three types of cluster testers, including square cluster testers, hexagonal cluster testers and circular cluster testers. The square rod bundle test piece and the hexagonal rod bundle test piece consist of three sub-channels of an inner channel, an edge and an angle, the circular rod bundle test piece consists of two sub-channels of the inner channel and one sub-channel of the edge, and different types of sampling probes are configured according to the shape structure of the specific sub-channels.
As shown in FIG. 3, the moving device in the reactor core assembly subchannel flow measurement testing device comprises a worm gear mechanism 111, a rotary joint 10, a gripping head 113, a Z-axis 114, a hand wheel 115, a lead screw 116, an X-axis 117 and a Y-axis 118.
The rotary joint 10 is positioned above a flange at the top of the corrugated pipe, the worm gear mechanism 111 is positioned at the upper part of the rotary joint 10 and fixedly connected with the rotary joint 10, the sampling probe is inserted into the rotary joint 10 and fixed, and the angle adjustment of the sampling probe is realized by rotating the worm gear mechanism 111; the gripping head 113 is fixedly connected with a flange at the top of the corrugated pipe; a main body part of the mobile device is built by three shafts, namely a Z shaft 114, an X shaft 117 and a Y shaft 118, the three shafts are provided with a hand wheel 115 and a lead screw 116, and the lead screw 116 is positioned at the center of each shaft and rotates through the hand wheel 115; the gripping head 113 is connected with a nut seat of a screw 116 of a Z-axis 114, the Z-axis 114 is buckled on an X-axis 117 and connected with the nut seat of the screw 116, the X-axis 117 is buckled on a Y-axis 118 and connected with the nut seat of the screw 116 of the Y-axis 118, and the movement of the gripping head 113 in the three-dimensional direction is realized by rotating a hand wheel 115 on each axis, so that the movement of the sampling probe is realized.
The foregoing is illustrative of the present invention only and is not to be construed as limiting thereof, and variations and modifications to the above-described embodiments, within the true spirit and scope of the invention, should be considered as within the scope of the claims of the present invention to those skilled in the art.
Claims (8)
1. A reactor core assembly subchannel flow measurement test device which characterized in that: the testing device comprises a rod bundle testing piece (5) for simulating a reactor core assembly sub-channel, wherein the rod bundle testing piece (5) is arranged in a rod bundle sleeve (4) and is fixed through a positioning piece (3) at the bottom end of the rod bundle sleeve (4); the rectifier (2) is positioned below the rod bundle sleeve (4), the lower cavity (1) is positioned at the lower part of the rectifier (2), and the rectifier (2) is used for straightening an inlet flow field; the visualization section (7) is arranged at the top of the rod bundle sleeve (4), and the top end of the rod bundle test piece (5) is positioned in the middle of the visualization section (7) and is connected with the bottom of the sampling probe (12), so that whether the sampling probe (12) is aligned with a sub-channel to be tested or not can be observed conveniently; the upper chamber (8) is positioned at the top of the visualization section (7) and used for returning water to a main loop; the top of the upper chamber (8) is connected with a corrugated pipe (9), and a rotary joint (10) is arranged at the center of a flange at the top of the corrugated pipe (9) and connected with a worm and gear mechanism arranged in the Z-axis direction of a moving device (11) to realize the rotation of a sampling probe (12); the sampling probe (12) is inserted into the rotary joint (10) and is fixedly connected through a small flange at the top of the rotary joint (10); a flange at the top of the corrugated pipe (9) is fixedly connected with a grabbing head at the lower end of a Z shaft of the moving device (11) to realize the movement of the sampling probe (12) in the three-dimensional direction; the rod bundle sleeve (4) is connected with the fixing frame (6) to realize the fixation of the test device; the inlet line of the lower chamber (1) and the outlet line of the upper chamber (8) are connected to the entire test circuit.
2. The reactor core assembly sub-channel flow measurement testing apparatus of claim 1, wherein: the visual section (7) is formed by processing a transparent material, the material performance meets the requirement of test working conditions, the top end height of the rod bundle test piece (5) is divided into an upper section and a lower section which are identical in geometric shape but different in flow cross section size, the cross section geometric dimension of the lower section is completely consistent with that of the rod bundle casing (4), the cross section geometric dimension of the upper section is larger than that of the lower section, the inner wall surface of the upper section is outwards widened by 1mm, the wall thickness of a sampling flow channel of the sampling probe (12) is considered, a space is reserved for the sampling probe (12) of the side and corner channel by widening the design of the flow cross section, and the sampling probe (12) of the side and corner channel can be aligned with the sub channel to be tested.
3. The reactor assembly sub-channel flow measurement testing apparatus of claim 1, wherein: the top end of the rod bundle test piece (5) is of a concave conical structure, the bottom end of the sampling probe (12) is of a convex conical structure with the same geometry, and the sampling probe (12) and the conical structure can be in butt joint in a matched mode, so that the sampling probe (12) can be aligned to a sub-channel to be tested.
4. The reactor core assembly sub-channel flow measurement testing apparatus of claim 1, wherein: the moving device (11) has four degrees of freedom, can realize the movement of any direction of a three-dimensional space and the adjustment of any angle of a horizontal plane, consists of an X shaft, a Y shaft and a Z shaft, realizes translation through a lead screw device, and realizes the angle adjustment of the sampling probe (12) on an X-Y plane by arranging a worm and gear mechanism in the Z shaft direction, wherein the adjusting process is manual or motor-driven, and the whole moving device (11) has high adjusting precision.
5. The reactor core assembly sub-channel flow measurement testing apparatus of claim 1, wherein: the rod bundle test piece (5) is fixed by a bottom fixing mode through a positioning piece (3) at the bottom of the rod bundle sleeve (4), and the outlet at the top end of the rod bundle test piece (5) is not restricted due to the fact that the flow of the opening channel needs to be measured; according to the actual situation, different component types can be added in the middle of the rod bundle test piece (5) for fixing by the positioning piece (3).
6. The reactor core assembly sub-channel flow measurement testing apparatus of claim 1, wherein: and a hole is formed in the side surface of the flange at the top of the corrugated pipe (9), a valve is welded, and high-point exhaust is realized at the test starting stage.
7. The reactor core assembly sub-channel flow measurement testing apparatus of claim 1, wherein: the sampling probe (12) is internally provided with a plurality of groups of pressure measuring pipes for measuring the static pressure of the sub-channel to be measured at the outlet of the rod bundle test piece (5) and the adjacent sub-channels thereof.
8. A method of testing a reactor core assembly subchannel flow measurement test apparatus of any of claims 1 to 7, characterized by: in the starting stage of the test loop, a main loop pump is started, test working media are pumped into the test device, and an exhaust valve of a corrugated pipe (9) is opened until air in the loop is exhausted; when no bubble exists in the visualization section (7), a plurality of groups of pressure measuring pipes in the sampling probe (12) are exhausted and connected with a differential pressure transmitter; after the exhaust work is finished, the position and the angle of the sampling probe (12) are adjusted by utilizing the mobile device (11), and the visual section (7) is observed to ensure that the sampling probe (12) is in butt joint with the sub-channel to be detected; the flow extracted by the sampling probe (12) is controlled by adjusting the opening of a valve connected with an outlet pipe of the sampling probe (12) to ensure that the static pressure of the sub-channel to be measured is the same as the average static pressure of all adjacent external sub-channels, at the moment, the flow extracted by the sampling probe (12) is the real flow of the sub-channel to be measured, and the flow measurement of the sub-channel to be measured is completed by recording the flow meter data on an outlet pipeline of the sampling probe (12) through a data acquisition system; then, the flow of the sub-channel at other positions is measured through the moving device (11), and when the angle of the next sub-channel to be measured and the angle of the previous sub-channel are changed, the angle of the sampling probe (12) is adjusted through a worm gear mechanism of the moving device (11).
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| WO2024051080A1 (en) * | 2022-09-08 | 2024-03-14 | 江苏核电有限公司 | Assembly for connecting cable to nuclear power station neutron temperature measurement channel |
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