Test piece for reactor measurement

Abstract

The invention provides a test piece for reactor measurement. The test piece for reactor measurement comprises: a water tank for simulating a prototype reactor pool; the reactor core shroud simulation piece comprises a square first cavity and an annular second cavity surrounding the first cavity, and the reactor core shroud simulation piece is flexibly connected with the water tank; the simulation reactor core assembly is used for reactor core flow distribution measurement and is arranged in the first cavity, the simulation reactor core assembly comprises a plurality of simulation fuel assemblies, and pressure guide pipes are arranged on the upper sides of the simulation fuel assemblies; a pressure guide pipe opening is formed in the upper side of the first cavity, and the pressure guide pipe discharges cooling water to the second cavity through the pressure guide pipe opening; and the reactor core supporting simulation piece is used for flow-induced vibration measurement, and the dead weight and the inherent frequency of the reactor core supporting simulation piece are the same as those of the prototype reactor.

Description

Technical Field

[0001] The invention relates to the field of nuclear reactors, and in particular to a test piece used for reactor measurement. Background Art

[0002] A pool-type research reactor is a type of reactor that can be used for multi-purpose purposes such as irradiation testing of fuel materials and isotope production.

[0003] Please refer to Figure 1 and Figure 2 , Figure 1 shows a schematic diagram of a pool-type research reactor, Figure 2 A schematic diagram of the prototype reactor is shown.

[0004] like Figure 1 As shown in the figure, the core is placed in the reactor pool, which is used to hold the core and also bears important cooling and shielding functions to ensure the safe operation of the reactor. The coolant flows from the reactor pool from top to bottom through the core, and the reactor pool relies on the natural circulation of the coolant to cool the core. When the reactor is running, the heat generated by the core is transferred to the coolant. Since the hot water has a lower density, it will naturally rise, and the cold water will sink to supplement, forming a natural circulation and taking away the heat of the core.

[0005] like Figure 2 As shown, the prototype reactor is located above the bottom plate of the reactor pool. The prototype reactor includes a heavy water tank, a core, and a core support structure. The core support structure provides guidance for the water flow and provides positioning and support for the fuel assembly. The core support structure may include a guide tube, an inner support tube, and an outer support tube that penetrate the interior of the prototype reactor. The cooling water flowing through the core flows out along the outlet pipe of the core support structure.

[0006] According to the requirements of the nuclear safety guideline HAD102 / 07 "Safety Design of Nuclear Power Plant Core", the design of the reactor internals must ensure that the coolant can be distributed to the fuel assemblies and related core structures in an appropriate proportion to provide the required cooling conditions. Therefore, it is necessary to carry out reactor flow distribution measurement tests and reactor internals flow-induced vibration measurement tests before the new reactor type is put into operation. The reactor flow distribution measurement test verifies that the core flow distribution meets the requirements of thermal and safety analysis, and the reactor internals flow-induced vibration measurement test verifies the structural integrity of the reactor internals under flow-induced vibration.

[0007] However, in the prior art, test pieces are separately designed and conducted for flow distribution measurement test and flow-induced vibration measurement test, respectively. Furthermore, the test pieces separately designed for flow distribution measurement test and flow-induced vibration measurement test are not easy to be combined, or the combination thereof may have a significant impact on the measurement result of the other test.

[0008] In order to overcome the above-mentioned defects of the prior art, the art is in urgent need of a test piece for reactor measurement, which can accurately measure the flow distribution measurement test and the flow-induced vibration measurement test at the same time, realize the sharing of the test piece and the simultaneous implementation of the test measurement, thereby greatly saving labor, testing and time costs and improving economic benefits. Summary of the invention

[0009] A brief summary of one or more aspects is given below to provide a basic understanding of these aspects. This summary is not an exhaustive overview of all conceived aspects, and is neither intended to identify the key or critical elements of all aspects nor to define the scope of any or all aspects. Its only purpose is to give some concepts of one or more aspects in a simplified form as a prelude to a more detailed description that will be given later.

[0010] In order to overcome the above-mentioned defects of the prior art, the present invention provides a test piece for reactor measurement, which can accurately measure the flow distribution measurement test and the flow-induced vibration measurement test at the same time, realize the sharing of the test piece and the synchronous implementation of the test measurement, thereby greatly saving labor, test and time costs and improving economic benefits.

[0011] Specifically, the test piece for reactor measurement provided according to the present invention includes: a water tank for simulating the water pool of the prototype reactor; a core barrel simulation piece, including a square first cavity and an annular second cavity surrounding the first cavity, and the core barrel simulation piece and the water tank are flexibly connected; a simulated core assembly, used for core flow distribution measurement, arranged in the first cavity, the simulated core assembly includes a plurality of simulated fuel assemblies, and a pressure pipe is provided on the upper side of the simulated fuel assembly; a pressure pipe opening is provided on the upper side of the first cavity, and the pressure pipe discharges cooling water to the second cavity through the pressure pipe opening; and a core support simulation piece, used for flow-induced vibration measurement, and the deadweight and natural frequency of the core support simulation piece are the same as those of the prototype reactor.

[0012] Preferably, in an embodiment of the present invention, the second cavity makes the mass and center of mass of the test piece consistent with those of the prototype reactor by means of additional counterweight.

[0013] Preferably, in an embodiment of the present invention, the additional weight is achieved by injecting water into the second cavity.

[0014] Preferably, in an embodiment of the present invention, the additional counterweight is achieved by increasing the mass of the metal cavity of the second cavity.

[0015] Preferably, in an embodiment of the present invention, the core shroud simulation member and the water tank are flexibly connected via a rubber sealing plate.

[0016] Preferably, in one embodiment of the present invention, the size of the simulated fuel assembly is consistent with that of the fuel assembly of the prototype reactor, and the simulated fuel assembly includes a flow meter, a resistance member and a resistance adjustment device from top to bottom to simulate the resistance coefficient of the fuel assembly of the prototype reactor and realize flow measurement.

[0017] Preferably, in an embodiment of the present invention, the pressure-guiding tube is a thin-walled metal tube.

[0018] Preferably, in one embodiment of the present invention, the structure, size, material and installation and fixing method of the core support simulation are the same as those of the prototype reactor, so that the deadweight and natural frequency of the core support simulation are the same as those of the prototype reactor.

[0019] Preferably, in an embodiment of the present invention, a plurality of sensors are provided in the core support simulation member to realize flow-induced vibration measurement, and the plurality of sensors include acceleration sensors, dynamic strain gauges and pressure pulsation sensors.

[0020] Preferably, in an embodiment of the present invention, the leads of the plurality of sensors are arranged along the cavity wall of the core support simulation member, and the open hole structure on the path of the leads is sealed by rubber. BRIEF DESCRIPTION OF THE DRAWINGS

[0021] The above features and advantages of the present invention can be better understood after reading the detailed description of the embodiments of the present disclosure in conjunction with the following drawings. In the drawings, the components are not necessarily drawn to scale, and components with similar related properties or features may have the same or similar reference numerals.

[0022] Figure 1 A schematic diagram of a pool-type research reactor is shown;

[0023] Figure 2 A schematic diagram of the structure of the prototype reactor is shown;

[0024] Figure 3 A schematic diagram of a test piece for reactor measurement provided according to some embodiments of the present invention is shown;

[0025] Figure 4 A cross-sectional view of a test piece for reactor measurement provided according to some embodiments of the present invention is shown;

[0026] Figure 5 A schematic diagram of a core shroud simulation of a test piece 300 provided according to some embodiments of the present invention is shown;

[0027] Figure 6 A schematic diagram showing a flexible connection between a core shroud simulation piece and a water tank of a test piece 300 provided according to some embodiments of the present invention is shown;

[0028] Figure 7 A schematic diagram showing a simulated fuel assembly of a test article 300 provided according to some embodiments of the present invention; and

[0029] Figure 8 A schematic diagram of a core support simulation of a test piece 300 provided according to some embodiments of the present invention is shown.

[0030] Reference numerals:

[0031] 300: test piece;

[0032] 301: rubber sealing plate;

[0033] 310: water tank;

[0034] 311: Import takeover;

[0035] 312: Steel platform;

[0036] 320: core shroud simulation parts;

[0037] 321: first cavity;

[0038] 322: second cavity;

[0039] 323: pressure pipe opening;

[0040] 330: core support simulation;

[0041] 331: inner support cylinder;

[0042] 332: load-bearing plate;

[0043] 333: grid plate;

[0044] 334: guide cylinder;

[0045] 335: outer support cylinder;

[0046] 340: Simulated core assembly;

[0047] 700: Simulated fuel assembly;

[0048] 710: flow meter;

[0049] 711: Throat;

[0050] 720: resistance member; and

[0051] 730: Resistance adjustment device. DETAILED DESCRIPTION

[0052] The present invention is described in detail below in conjunction with the accompanying drawings and specific embodiments. Note that the aspects described below in conjunction with the accompanying drawings and specific embodiments are only exemplary and should not be construed as limiting the scope of protection of the present invention in any way.

[0053] In the description of the present invention, it should be noted that, unless otherwise clearly specified and limited, the terms "installed", "connected", and "connected" should be understood in a broad sense, for example, it can be a fixed connection, a detachable connection, or an integral connection; it can be a mechanical connection or an electrical connection; it can be a direct connection, or it can be indirectly connected through an intermediate medium, or it can be the internal communication of two components. For ordinary technicians in this field, the specific meanings of the above terms in the present invention can be understood according to specific circumstances.

[0054] In addition, the terms "upper", "lower", "left", "right", "top", "bottom", "horizontal" and "vertical" used in the following description should be understood as the directions shown in the paragraph and the related drawings. Such relative terms are only used for the convenience of description and do not mean that the device described therein must be manufactured or operated in a specific direction, and therefore should not be understood as limiting the present invention.

[0055] It is understood that although the terms "first", "second", "third", etc. may be used herein to describe various components, regions, layers and / or parts, these components, regions, layers and / or parts should not be limited by these terms, and these terms are only used to distinguish different components, regions, layers and / or parts. Therefore, the first component, region, layer and / or part discussed below may be referred to as a second component, region, layer and / or part without departing from some embodiments of the present invention.

[0056] As described above, the prior art designs test pieces and conducts tests separately for flow distribution measurement test and flow-induced vibration measurement test, and the test pieces designed separately for flow distribution measurement test and flow-induced vibration measurement test are not easy to combine or the combination may have a significant impact on the measurement results of the other test.

[0057] In order to overcome the above-mentioned defects of the prior art, the present invention provides a test piece for reactor measurement, which can accurately measure the flow distribution measurement test and the flow-induced vibration measurement test at the same time, realize the sharing of the test piece and the synchronous implementation of the test measurement, thereby greatly saving labor, test and time costs and improving economic benefits.

[0058] Please refer to Figure 3 and Figure 4 , Figure 3 A schematic diagram of a test piece for reactor measurement provided according to some embodiments of the present invention is shown. Figure 4A cross-sectional view of a test piece for reactor measurement provided according to some embodiments of the present invention is shown.

[0059] like Figure 3 and Figure 4 As shown, the test piece 300 for reactor measurement may include a water tank 310 for simulating a prototype reactor water pool, a core barrel simulation 320, and a core support simulation 330. The core barrel simulation 320 may be provided with a simulated core assembly 340 for simulating a prototype reactor core.

[0060] The prototype reactor is generally located under a reactor pool more than ten meters deep. The test piece 300 simulates the reactor pool of the prototype reactor through a water tank 310 of sufficient size. The water tank 310 has inlet pipes 311 arranged symmetrically, thereby providing a uniform inlet flow condition for the test piece 300.

[0061] Please refer to Figure 4 and Figure 5 , Figure 5 A schematic diagram of a core shroud simulation of a test piece 300 provided according to some embodiments of the present invention is shown.

[0062] like Figure 4 and Figure 5 As shown, the core shroud simulation 320 may include a square first cavity 321 and an annular second cavity 322 surrounding the first cavity 321 .

[0063] like Figure 4 As shown, the first cavity 321 of the core shroud simulation 320 is used to arrange the simulated core assembly 340, and the second cavity 322 is a simplified prototype reactor structure, which is used to simulate the heavy water tank of the prototype reactor. The simplified structure and size of the core shroud simulation 320 are consistent with the prototype reactor to ensure that the hydraulic characteristics of the simulated reactor main flow channel in the test piece 300 are consistent with the main flow channel of the prototype reactor.

[0064] The second cavity 322 of the core shroud simulation part 320 can make the mass and center of mass of the test piece 300 consistent with those of the prototype reactor by means of additional counterweight. In some embodiments, the additional counterweight can be achieved by injecting water into the second cavity 322. In other embodiments, the additional counterweight can be achieved by increasing the mass of the metal cavity of the second cavity 322, for example, by thickening the thickness of the stainless steel outer wall. Thus, by means of additional counterweight, the core shroud simulation part 320 can adjust the overall mass of the test piece 300 and ensure that the overall mass of the test piece 300 is consistent with that of the prototype reactor.

[0065] Please refer to Figure 4 and Figure 6 , Figure 6A schematic diagram showing the flexible connection between the core shroud simulation and the water tank of the test piece 300 provided according to some embodiments of the present invention is shown.

[0066] The first cavity 321 of the core shroud simulation 320 is flexibly connected to the water tank 310. Figure 6 As shown, the water tank 310 can bear the weight through the steel platform 312 , and the core shroud simulation part 320 and the steel platform 312 of the water tank 310 are flexibly connected through the rubber sealing plate 301 .

[0067] In other embodiments, the rubber sealing plate 301 can be realized by other flexible connection methods such as a rubber expansion joint.

[0068] In this way, the water tank 310 can be isolated from the core and core support structure 330 of the test piece 300 through the flexible connection between the core shroud simulation part 320 and the water tank 310, thereby avoiding affecting the natural frequency of the internal components of the reactor, and further avoiding affecting the flow-induced vibration response of the core support structure 330.

[0069] like Figure 4 As shown, the first cavity 321 of the core shroud simulation part 320 can be used to arrange a simulated core assembly 340. The simulated core assembly 340 can include a plurality of simulated fuel assemblies, and the number of simulated fuel assemblies is consistent with the number of prototype reactors. The simulated core assembly 340 can implement a core flow distribution measurement test by measuring the inlet flow through the plurality of simulated fuel assemblies.

[0070] Please refer to Figure 7 , Figure 7 A schematic diagram of a simulated fuel assembly of a test article 300 provided in accordance with some embodiments of the present invention is shown.

[0071] In some embodiments, the simulated fuel assembly of the test article 300 may be as follows: Figure 7 The simulated fuel assembly 700 has the same size as the fuel assembly of the prototype reactor, and may include a flow meter 710, a resistance member 720, and a resistance adjustment device 730 from top to bottom to simulate the resistance coefficient of the fuel assembly of the prototype reactor and realize flow measurement.

[0072] The inlet of the simulated fuel assembly 700 may be provided with a grid baffle, and a flow meter 710 may be provided below the grid baffle. The flow meter 710 may be a venturi tube, and in other embodiments, may be replaced by other types of flow measurement devices. The resistance member 720 may be a plate bundle area, and in other embodiments, may be replaced by a resistance member such as a porous plate. The resistance adjustment device 730 may be a structure composed of a throttle ring and an adjustment cone, and the overall resistance coefficient of the simulated fuel assembly 700 is controlled by adjusting the position of the adjustment cone. In other embodiments, the resistance adjustment device 730 may also be replaced by a resistance adjustment device of other structural types.

[0073] In this way, the resistance coefficient of the simulated fuel assembly 700 can be roughly matched with that of the fuel assembly of the prototype reactor through the resistance member 720, and then the resistance adjustment device 730 can be used to achieve precise adjustment so that the total resistance coefficient of the simulated fuel assembly 700 is the same as that of the fuel assembly of the prototype reactor, so that the flow rate flowing into each group of simulated fuel assemblies 700 can represent the fuel assembly of the prototype reactor. Then, the flow rate in the simulated fuel assembly 700 is measured by the calibrated built-in flow meter 710, and the flow distribution test can be completed to verify whether the core flow distribution of the prototype reactor meets the requirements.

[0074] In addition, the uniformity of the core inlet flow rate can be achieved by configuring the top water tank 310, and combined with the grid partition of the simulated fuel assembly 700, the uniform flow of the inlet flow of the simulated fuel assembly can be further achieved.

[0075] In addition, in the fuel assembly of the pool-type research reactor, the pressure-inducing tube is mainly used to monitor the pressure inside the fuel assembly. During the operation of the fuel assembly, the internal coolant (usually water) will be affected by the heat of the core, and the temperature and pressure will change. The pressure-inducing tube can lead the pressure inside the fuel assembly. Existing pressure-inducing tubes will have connecting devices such as buckles on the core support structure, which will affect the measurement of the flow-induced vibration test. The pressure-inducing tube of the test piece 300 provided by the present invention can be arranged on the upper side of the simulated fuel assembly. The pressure-inducing tube can be connected at one end to the position where the pressure needs to be monitored inside the fuel assembly, and at the Figure 7 In the simulated fuel assembly shown, one end of the impulse pressure tube can be set at the throat 711 of the flow meter 710 of the simulated fuel assembly 700, and the other end can be set at the grid baffle position at the inlet of the simulated fuel assembly. When the internal pressure of the simulated fuel assembly 700 changes, the pressure can be transmitted to the inlet grid baffle position of the simulated fuel assembly 700 through the medium (usually coolant) in the impulse pressure tube.

[0076] Please combine Figures 4 to 6, a pressure-inducing pipe opening 323 may be provided on the upper side of the first cavity 321 of the core shroud simulation 320. The inlet of the simulated fuel assembly is located below the pressure-inducing pipe opening 323. The pressure-inducing pipe may continue to extend from the inlet of the simulated fuel assembly to the second cavity 322 through the pressure-inducing pipe opening 323. When the internal pressure of the simulated fuel assembly 700 changes, the cooling water in the pressure-inducing pipe is conducted to the inlet grid baffle position of the simulated fuel assembly 700, and then continues to be discharged to the second cavity 322 through the pressure-inducing pipe opening 323.

[0077] In this way, through the planning of the pressure tube arrangement and the lead path, the test piece 300 for reactor measurement provided by the present invention does not add additional constraint connections between the core support structure and the simulated fuel assembly and the simulated core assembly, thereby realizing the flow distribution measurement test without affecting the measurement of flow-induced vibration.

[0078] Furthermore, the pressure-inducing tube may be a thin-walled metal tube. The use of a thin-walled metal tube can make the rigidity of the pressure-inducing tube negligible compared to the rigidity of the test piece 300 body, thereby effectively reducing the impact on the dynamic characteristics of the test piece 300.

[0079] The test piece 300 for reactor measurement may include a core support simulation piece 330 for flow-induced vibration measurement, and the deadweight and natural frequency of the core support simulation piece 300 are the same as those of the prototype reactor. The core support structure of the prototype reactor can be used to provide guidance for the water flow of the reactor, and can also be used to provide positioning and support for the fuel assembly. In some embodiments, the structure, size, material and installation and fixing method of the core support simulation piece 330 are the same as those of the prototype reactor, so that the deadweight and natural frequency of the core support simulation piece 330 are the same as those of the prototype reactor.

[0080] Please refer to Figure 8 , Figure 8 A schematic diagram of a core support simulation of a test piece 300 provided according to some embodiments of the present invention is shown.

[0081] like Figure 8 As shown, a grid plate 333 is arranged on the load-bearing plate 332 of the inner support cylinder 331 of the core support simulation 330. A guide cylinder 334 is inserted into the grid plate 333. The simulated fuel assembly is also inserted into the grid plate 333. In addition, components such as a neutron source can also be inserted into the grid plate 333. The guide cylinder 334 can include a follower fuel assembly and a control rod assembly, and the follower fuel assembly and the control rod assembly can move up and down in the guide cylinder 334.

[0082] Multiple sensors may be provided in the core support simulation 330 to achieve flow-induced vibration measurement. The multiple sensors may include an acceleration sensor, a dynamic strain gauge, and a pressure pulsation sensor. The multiple sensors may be provided at a measurement location, and the measurement location may include an inner support cylinder 331, an outer support cylinder 335, a guide cylinder 334, and a bearing plate 332. The multiple sensors may be connected to an external data acquisition system including data acquisition analysis and processing software.

[0083] In some embodiments, the acceleration measurement components can be arranged in two directions of 90° azimuth apart on the XY plane at the same elevation position of the Z axis, which plays a role of mutual verification and redundancy. The dynamic strain gauge can be preferably attached to the position with the largest strain, and the position with the largest strain can be determined based on the vibration and displacement response. The dynamic strain gauge may include a dynamic strain gauge attached to a cylindrical structure and a beam-type structure. Based on the strain direction, the dynamic strain gauge attached to the cylindrical structure can consider the axial and circumferential vibration directions when pasting, and the dynamic strain gauge attached to the beam-type structure can consider the axial direction when pasting. In addition, the position and number of the dynamic strain gauges can be arranged based on the principle of using 2 to prepare 2. The pressure pulsation sensor can be used to measure the fluid load at the outlet position of the inner support cylinder 331, and the position and number of the pressure pulsation sensor can be arranged based on the principle of using 1 to prepare 2.

[0084] In addition, the leads of multiple sensors can be arranged along the cavity wall of the core support simulation 330, and the opening structure on the path of the leads can be sealed by rubber. In this way, the test piece 300 can meet the requirements of flow-induced vibration measurement while avoiding blocking of key main flow channels and generation of additional bypass flow, and does not affect the measurement of flow distribution test.

[0085] In some embodiments, flow field analysis can be performed based on CFD (Computational Fluid Dynamics) technology to compare and adjust the flow field distribution of the test piece with the actual flow field distribution of the prototype reactor to ensure that the flow field distribution of the test piece 300 is consistent with that of the actual reactor.

[0086] In addition, in some embodiments, dynamic characteristics analysis can be carried out on simplified non-core support structures (i.e., core shroud simulation parts, simulated core assemblies) compared with the actual structure of the prototype reactor to ensure that the main frequencies and vibration modes of the simplified non-core support structures are consistent with those of the actual prototype reactor.

[0087] In summary, compared with the prior art practice of separately designing test pieces and conducting tests for flow distribution measurement tests and flow-induced vibration measurement tests, the test piece for reactor measurement provided by the present invention can combine the measurement of flow distribution test and the measurement of flow-induced vibration test into one, thereby realizing the sharing of test pieces and the simultaneous implementation of test measurements, and ensuring that the measurement results of flow distribution test and flow-induced vibration test can characterize the prototype reactor, thereby greatly saving labor, test and time costs and improving economic benefits.

[0088] The previous description of the disclosure is provided to enable any person skilled in the art to make or use the disclosure. Various modifications to the disclosure will be apparent to those skilled in the art, and the general principles defined herein may be applied to other variations without departing from the spirit or scope of the disclosure. Thus, the disclosure is not intended to be limited to the examples and designs described herein, but should be granted the widest scope consistent with the principles and novel features disclosed herein.

Claims

1. A test piece for reactor measurement, characterized in that: include: water tanks, used to simulate prototype reactor pools; A core shroud simulation piece, comprising a square first cavity and an annular second cavity surrounding the first cavity, wherein the core shroud simulation piece is flexibly connected to the water tank; A simulated core assembly, used for measuring core flow distribution, is disposed in the first cavity, the simulated core assembly comprises a plurality of simulated fuel assemblies, and a pressure-inducing pipe is disposed on the upper side of the simulated fuel assembly; A pressure-inducing pipe opening is provided on the upper side of the first cavity, and the pressure-inducing pipe discharges cooling water to the second cavity through the pressure-inducing pipe opening; and A core support simulation is used for flow-induced vibration measurement, wherein the deadweight and natural frequency of the core support simulation are the same as those of the prototype reactor.

2. The test piece for reactor measurement according to claim 1, characterized in that: The second cavity is provided with an additional counterweight to ensure that the mass and center of mass of the test piece are consistent with those of the prototype reactor.

3. The test piece for reactor measurement according to claim 2, characterized in that: Additional weight is achieved by filling the second cavity with water.

4. The test piece for reactor measurement according to claim 2, characterized in that: The additional weight is achieved by increasing the mass of the metal cavity of the second cavity.

5. The test piece for reactor measurement according to claim 1, characterized in that: The core shroud simulation component and the water tank are flexibly connected via a rubber sealing plate.

6. The test piece for reactor measurement according to claim 1, characterized in that: The size of the simulated fuel assembly is consistent with that of the fuel assembly of the prototype reactor. The simulated fuel assembly includes a flow meter, a resistance member and a resistance adjustment device from top to bottom to simulate the resistance coefficient of the fuel assembly of the prototype reactor and realize flow measurement.

7. The test piece for reactor measurement according to claim 1, characterized in that: The pressure-inducing pipe is a thin-walled metal pipe.

8. The test piece for reactor measurement according to claim 1, characterized in that: The structure, size, material and installation and fixing method of the core support simulation are the same as those of the prototype reactor, so that the deadweight and natural frequency of the core support simulation are the same as those of the prototype reactor.

9. The test piece for reactor measurement according to claim 1, characterized in that: A plurality of sensors are arranged in the core support simulation part to realize flow-induced vibration measurement, and the plurality of sensors include acceleration sensors, dynamic strain gauges and pressure pulsation sensors.

10. The test piece for reactor measurement according to claim 9, characterized in that: Lead wires of the plurality of sensors are arranged along the cavity wall of the core support simulation component, and the open hole structure on the path of the lead wires is sealed by rubber.

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