Cooling liquid flow measuring device of sodium-cooled fast reactor assembly simulation part

Abstract

The embodiment of the invention discloses a cooling liquid flow measuring device of a sodium-cooled fast reactor assembly simulation part. The device comprises a fast reactor assembly simulation experiment module, a cooling liquid circulation module, a flow acquisition module and a data acquisition module. Wherein the fast reactor assembly simulation experiment module comprises a fast reactor assembly simulation piece, and the fast reactor assembly simulation piece comprises a hexagonal outer sleeve; two cross sections with different positions are arranged in the axial direction of the hexagonal outer sleeve to serve as a first pressure testing surface and a second pressure testing surface; a first pressure testing hole is formed in each of six side walls, corresponding to the first pressure testing surface, of the hexagonal outer sleeve; the six first pressure testing holes are communicated with one another, and the six side walls, corresponding to the second pressure testing surfaces, of the hexagonal outer sleeve are each provided with a second pressure testing hole; the six second pressure testing holes are communicated with one another; the data acquisition module is configured to detect the pressure drop between the first pressure testing surface and the second testing surface, and the cooling liquid flow is calculated according to the pressure drop.

Description

Technical Field

[0001] The invention belongs to the technical field of nuclear energy, and in particular relates to a coolant flow measurement device for a sodium-cooled fast reactor assembly simulation part. Background Art

[0002] The sodium-cooled fast reactor is a type of nuclear power reactor. The pool-type primary cooling system mainly includes key components such as sodium pumps, large grid plate headers, small grid plate headers and in-pile components. After the cooling sodium liquid is distributed through the large grid plate headers and small grid plate headers, it enters the in-pile components through the tube pin openings and takes away the heat generated by the fuel rod bundles inside the components. The sodium-cooled fast reactor components are the core components of nuclear power reactors. Their thermal hydraulic characteristics are related to the flow distribution of the nuclear power reactor system and play a decisive role in the safety of nuclear power reactors. Sodium-cooled fast reactors are divided into fuel assemblies, shielding assemblies and control rod assemblies according to their functions. The thermal power of different types of components varies greatly, so the allocated cooling sodium liquid flow also varies greatly. In order to avoid the lateral mixing of cooling sodium liquid between different components and improve the overall thermal efficiency of the nuclear power reactor, the component rod bundle of the sodium-cooled fast reactor component is set in a hexagonal outer sleeve, and an independent cooling flow channel is formed between the hexagonal sleeve of each box component and the component rod bundle. When the flow rate of cooling sodium liquid in the cooling channel is too large, its outlet temperature is too low, resulting in poor economic efficiency of the nuclear power reactor; when the flow rate of cooling sodium liquid in the cooling channel is too small, it is easy to cause the cladding of the component rod bundle to be damaged or even melted, thereby threatening the safety of the nuclear power reactor. Therefore, studying the overall flow distribution characteristics of sodium-cooled fast reactor components under different operating conditions to ensure that the flow rate of cooling sodium liquid in each box of components is both economical and safe is the key to the design and development of sodium-cooled fast reactors.

[0003] Since the pool-type primary cooling system has many components and a complex structure, the flow conditions of the internal coolant are complex. It is difficult to accurately simulate the internal flow field and the flow distribution characteristics of the reactor components using theoretical analysis and numerical calculations. It is necessary to carry out an out-of-pile hydraulic test of the sodium-cooled fast reactor components. The out-of-pile hydraulic test of the sodium-cooled fast reactor components uses deionized water instead of liquid sodium as the coolant, and is carried out using a sodium-cooled fast reactor component simulation with a model scale of 1:1; the flow distribution characteristics of the sodium-cooled fast reactor component simulation require real-time measurement of the deionized water flow through different components.

[0004] At present, the coolant flow measurement of the sodium-cooled fast reactor assembly simulator mostly adopts velocity flow meters such as built-in turbine flowmeter, external vortex flowmeter and electromagnetic flowmeter. On the one hand, the disturbance is relatively large, which will change the overall flow resistance characteristics of the sodium-cooled fast reactor assembly simulator; on the other hand, in order to ensure the measurement accuracy of the velocity flowmeter, it is necessary to set a straight pipe section with ten times the pipe diameter at the front and five times the pipe diameter at the back, but the sodium-cooled fast reactor assembly simulator cannot meet the aforementioned straight pipe section requirements, so the measurement accuracy is not high. Summary of the invention

[0005] In view of this, the technical solution disclosed in some embodiments is a coolant flow measurement device for a sodium-cooled fast reactor assembly simulation component, the measurement device comprising:

[0006] Fast reactor assembly simulation experiment module, used to simulate the flow measurement conditions of the sodium-cooled fast reactor assembly simulation parts;

[0007] A coolant circulation module is arranged to be connected to the fast reactor assembly simulation experiment module and is used to provide the fast reactor assembly simulation experiment module with coolant that meets set conditions;

[0008] A flow acquisition module is arranged to be connected to the fast reactor assembly simulation experiment module and the coolant circulation module respectively, and is used to measure the coolant flow flowing through the fast reactor assembly simulation experiment module;

[0009] A data acquisition module is provided, connected to the flow acquisition module and the fast reactor component simulation experiment module respectively, and is used for collecting and processing data;

[0010] The fast reactor component simulation experiment module includes:

[0011] A fast reactor assembly simulation part, comprising an operating head, an upper transition joint, a hexagonal outer sleeve, a lower transition joint and a tube pin that are arranged to be connected in sequence;

[0012] The bottom support structure of the simulation part is arranged at the bottom of the fast reactor assembly simulation part and is adapted to be installed and fixed with the tube pins;

[0013] The top support structure of the simulation component is arranged on the top of the fast reactor assembly simulation component and is adapted to be installed and fixed with the operating head;

[0014] Two cross sections at different positions are arranged in the axial direction of the hexagonal outer sleeve as a first pressure test surface and a second pressure test surface;

[0015] A first pressure test hole is respectively arranged on the six side walls of the hexagonal outer sleeve corresponding to the first pressure test surface; the six first pressure test holes are arranged to be interconnected, and are further arranged to be connected to the data acquisition module;

[0016] A second pressure test hole is respectively arranged on the six side walls of the hexagonal outer sleeve corresponding to the second pressure test surface; the six second pressure test holes are arranged to be interconnected, and are further arranged to be connected to the data acquisition module; the data acquisition module is configured to detect the pressure drop between the first pressure test surface and the second test surface, and obtain the coolant flow rate based on the pressure drop calculation.

[0017] Further, in some embodiments, the coolant flow measurement device of the sodium-cooled fast reactor assembly simulation component disclosed, the coolant circulation module includes:

[0018] A water tank is used to store coolant deionized water; a water level gauge is provided in the water tank, and a heating pipe is provided at the bottom of the water tank to heat the deionized water in the water tank;

[0019] A temperature adjustment control component is arranged to be connected to the heating tube and is used to control the heating tube;

[0020] A deionized water production component is arranged to be connected to the water tank and is used to generate deionized water and transport it to the water tank;

[0021] A water level control component is connected to the water level meter and the deionized water production component to control the water level of the deionized water in the water tank;

[0022] A circulating water pump is connected to the water tank. The circulating water pump is connected to the fast reactor assembly simulation component and is used to transport deionized water from the water tank to the fast reactor assembly simulation component.

[0023] In some embodiments, the coolant flow measurement device of the sodium-cooled fast reactor assembly simulation part disclosed in the invention comprises a flow acquisition module comprising:

[0024] A flow meter, wherein the flow meter is provided with a flow meter solenoid valve matched therewith;

[0025] The inlet end of the flow meter is arranged to be connected to the coolant outlet of the fast reactor assembly simulation part, and the outlet end of the flow meter is arranged to be connected to the water tank. The flow meter is configured to detect the coolant flow rate flowing from the fast reactor assembly simulation part to the water tank.

[0026] Some embodiments disclose a coolant flow measurement device for a sodium-cooled fast reactor assembly simulation component, wherein a plurality of flow meters are provided, and each flow meter has a different measurement range.

[0027] In some embodiments, the coolant flow measurement device of the sodium-cooled fast reactor assembly simulation part disclosed in the present invention comprises a data acquisition module:

[0028] Pressure collection components;

[0029] The data acquisition control component is connected to the pressure acquisition component and configured to control the pressure acquisition component to collect pressure data. The data acquisition control component is connected to the flow acquisition module and configured to control the flow acquisition module to collect coolant flow data.

[0030] Among them, the pressure collection component includes a differential pressure sensor and a matching pressure sensor solenoid valve. The high-pressure test port of the differential pressure sensor is arranged to be connected to the first pressure test hole, and the low-pressure test port of the differential pressure sensor is arranged to be connected to the second pressure test hole.

[0031] In some embodiments, a coolant flow measurement device for a sodium-cooled fast reactor assembly simulation component is provided with a plurality of differential pressure sensors, each of which has a different measurement range.

[0032] Some embodiments disclose a coolant flow measurement device for a sodium-cooled fast reactor assembly simulation component, wherein six first pressure test holes are arranged to be connected to a first connecting pipe, the first connecting pipe is sleeved outside a hexagonal outer sleeve, the first connecting pipe is arranged to be connected to a first pressure main pipe, and the first pressure main pipe is arranged to be connected to a high-pressure test port of the differential pressure sensor; six second pressure test holes are arranged to be connected to a second connecting pipe, the second connecting pipe is sleeved outside a hexagonal outer sleeve, the second connecting pipe is arranged to be connected to a second pressure main pipe, and the second pressure main pipe is arranged to be connected to a low-pressure test port of the differential pressure sensor.

[0033] In some embodiments of the coolant flow measurement device for the sodium-cooled fast reactor assembly simulation component disclosed, the first pressure test surface is closer to the fluid upstream end of the hexagonal outer sleeve, and the second pressure test surface is closer to the fluid downstream end of the hexagonal outer sleeve.

[0034] In some embodiments of the coolant flow measurement device for the sodium-cooled fast reactor assembly simulation component disclosed, the first pressure test hole is arranged in the middle position of the side wall of the hexagonal outer sleeve; the second pressure test hole is arranged in the middle position of the side wall of the hexagonal outer sleeve.

[0035] In some embodiments of the coolant flow measurement device for the sodium-cooled fast reactor assembly simulation component disclosed, the distance between the first pressure test surface and the second pressure test surface is not less than two-thirds of the length of the hexagonal outer sleeve.

[0036] The coolant flow measurement device of a sodium-cooled fast reactor assembly simulation component disclosed in an embodiment of the present invention has two pressure test surfaces at two different axial positions of a hexagonal outer sleeve of the fast reactor assembly simulation component, and further has a pressure test hole respectively arranged on the six side surfaces of the hexagonal outer sleeve. The flow rate of the coolant fluid is accurately obtained by measuring the pressure drop by utilizing the relationship between the pressure drop and the flow rate formed between the two force test surfaces when the coolant fluid flows through the hexagonal outer sleeve. The disturbance to the flow field is small and the measurement accuracy is high. The device can provide reliable technical support for an off-core hydraulic test of a sodium-cooled fast reactor core flow distribution, and has good application prospects in the coolant flow measurement of a sodium-cooled fast reactor assembly simulation component. BRIEF DESCRIPTION OF THE DRAWINGS

[0037] Figure 1 A schematic diagram of coolant flow measurement of a sodium-cooled fast reactor assembly simulation component disclosed in Example 1;

[0038] Figure 2 A schematic diagram of the test structure setting of the first pressure test surface disclosed in Example 1;

[0039] Figure 3 A schematic diagram of the test structure setting of the second pressure test surface disclosed in Example 1;

[0040] Figure 4A top view of the first pressure test surface structure disclosed in Example 1;

[0041] Figure 5 This is a schematic diagram of the coolant flow measurement device disclosed in Example 2.

[0042] Reference numerals

[0043] 1 Operating head 2 Upper transition joint

[0044] 3 Hexagonal outer sleeve 4 Lower transition joint

[0045] 5 Pin 6 First pressure test surface

[0046] 7 Second pressure test surface 8 Differential pressure sensor

[0047] 61 First pressure test hole 62 First pressure test tube

[0048] 63 First connecting pipe 64 First pressure main pipe

[0049] 71 Second pressure test hole 72 Second pressure test tube

[0050] 73 Second connecting pipe 74 Second pressure main pipe

[0051] 10 Component rod cluster 100 Fast reactor component simulation test module

[0052] 200 Coolant circulation module 300 Data acquisition module

[0053] 400 Flow collection module 101 Simulation bottom support structure

[0054] 102 Simulation top support structure 201 Water level control component

[0055] 202 Water level gauge 203 Water tank

[0056] 204 Circulating water pump 205 Heating pipe

[0057] 206 Water temperature regulation and control component 207 Deionized water production component

[0058] 301 Data acquisition control component 302 Pressure acquisition component

[0059] 3021 Pressure sensor solenoid valve 3022 Differential pressure sensor

[0060] 401 Flow meter solenoid valve 402 Flow meter

[0061] 10 Component rod cluster 103 Fast reactor component simulation DETAILED DESCRIPTION

[0062] The word "embodiment" used herein as an "exemplary" does not necessarily mean that any embodiment described is superior or better than other embodiments. Performance index tests in the embodiments of the present invention are performed using conventional test methods in the art unless otherwise specified. It should be understood that the terms described in the embodiments of the present invention are only used to describe specific implementation methods and are not intended to limit the contents disclosed in the embodiments of the present invention.

[0063] Unless otherwise specified, the technical and scientific terms used herein have the same meanings as commonly understood by ordinary technicians in the technical field to which the embodiments of the present invention belong; other experimental methods and technical means not specifically specified in the embodiments of the present invention refer to experimental methods and technical means commonly used by ordinary technicians in the field.

[0064] The terms "substantially" and "approximately" used herein are used to describe small fluctuations. For example, they can refer to less than or equal to ±5%, such as less than or equal to ±2%, such as less than or equal to ±1%, such as less than or equal to ±0.5%, such as less than or equal to ±0.2%, such as less than or equal to ±0.1%, such as less than or equal to ±0.05%. The numerical data represented or presented in the range format herein are used only for convenience and brevity, and should therefore be flexibly interpreted as including not only the values ​​clearly listed as the limits of the range, but also all independent values ​​or sub-ranges contained in the range. For example, the numerical range of "1-5%" should be interpreted as including not only the clearly listed values ​​of 1% to 5%, but also the independent values ​​and sub-ranges within the range shown. Therefore, independent values ​​such as 2%, 3.5% and 4% and sub-ranges such as 1%-3%, 2%-4% and 3%-5% are included in this numerical range. This principle also applies to the range of only one numerical value. In addition, such an interpretation applies regardless of the width of the range or the characteristics described.

[0065] In this document, including in the claims, transitional words such as "comprises," "includes," "with," "having," "containing," "involving," "accommodating," etc. are understood to be open-ended, i.e., meaning "including but not limited to." Only the transitional words "consisting of" and "composed of" are closed transitional words.

[0066] In order to better illustrate the present invention, numerous specific details are provided in the specific examples below. It should be understood by those skilled in the art that the present invention can be implemented without certain specific details. In the embodiments, some methods, means, instruments, equipment, etc. well known to those skilled in the art are not described in detail in order to highlight the gist of the present invention.

[0067] Under the premise of no conflict, the technical features disclosed in the embodiments of the present invention may be arbitrarily combined, and the resulting technical solutions belong to the contents disclosed in the embodiments of the present invention.

[0068] In some embodiments, the coolant flow measurement device of the sodium-cooled fast reactor assembly simulation comprises:

[0069] Fast reactor assembly simulation experiment module, used to simulate the flow measurement conditions of fast reactor assembly simulation parts;

[0070] A coolant circulation module is arranged to be connected to the fast reactor assembly simulation experiment module and is used to provide the fast reactor assembly simulation experiment module with coolant that meets set conditions;

[0071] A flow acquisition module is arranged to be connected to the fast reactor assembly simulation experiment module and the coolant circulation module respectively, and is used to measure the coolant flow flowing through the fast reactor assembly simulation experiment module;

[0072] A data acquisition module is provided, connected to the flow acquisition module and the fast reactor component simulation experiment module respectively, and is used for collecting and processing data;

[0073] The fast reactor component simulation experiment module includes:

[0074] The fast reactor assembly simulation part includes an operating head, an upper transition joint, a hexagonal outer sleeve, a lower transition joint and a tube pin which are connected in sequence; wherein the operating head is connected to the upper transition joint, which is used for loading and unloading the fast reactor assembly simulation part on the one hand, and serves as a coolant outlet of the fast reactor assembly simulation part on the other hand; a positioning block is arranged on the outer side of the upper transition joint to ensure the radial positioning between the fast reactor assembly simulation parts; a component rod bundle is arranged in the hexagonal outer sleeve to form a coolant flow area in the fast reactor assembly simulation part; the lower transition joint is the connection part between the fast reactor assembly simulation part and its supporting structure, and its contact surface is mostly a spherical surface or a conical surface, which can ensure the sealing of the assembly flow and a certain leakage flow; the tube pin is located at the lower part of the lower transition joint, which is not only the coolant inlet of the fast reactor assembly simulation part, but also adjusts the leakage flow through different sealing structures, and also has the function of positioning the fast reactor assembly simulation part. Under the conditions of the out-of-core hydraulic test, the coolant deionized water enters from the coolant inlet on the tube pin, passes through the lower transition joint, the hexagonal outer sleeve and the upper transition joint, and finally flows out from the coolant outlet of the operating head;

[0075] The bottom support structure of the simulation part is arranged at the bottom of the fast reactor assembly simulation part and is adapted to be installed and fixed with the tube pins;

[0076] The top support structure of the simulation part is arranged on the top of the fast reactor assembly simulation part and is adapted to be installed and fixed with the operating head;

[0077] Two cross sections at different positions are arranged in the axial direction of the hexagonal outer sleeve as a first pressure test surface and a second pressure test surface;

[0078] A first pressure test hole is respectively arranged on the six side walls of the hexagonal outer sleeve corresponding to the first pressure test surface; the six first pressure test holes are arranged to be interconnected, and are further arranged to be connected to the data acquisition module;

[0079] A second pressure test hole is respectively arranged on the six side walls of the hexagonal outer sleeve corresponding to the second pressure test surface; the six second pressure test holes are arranged to be interconnected, and are further arranged to be connected to the data acquisition module; the data acquisition module is configured to detect the pressure drop between the first pressure test surface and the second test surface, and calculate the coolant flow rate according to the pressure drop;

[0080] The coolant circulation module includes:

[0081] A water tank is used to store coolant deionized water; a water level gauge is provided in the water tank, and a heating pipe is provided at the bottom of the water tank to heat the deionized water in the water tank;

[0082] A temperature adjustment control component is arranged to be connected to the heating tube and is used to control the heating tube;

[0083] A deionized water production component is arranged to be connected to the water tank and is used to generate deionized water and transport it to the water tank;

[0084] A water level control component is connected to the water level meter and the deionized water production component to control the water level of the deionized water in the water tank;

[0085] A circulating water pump is connected to the water tank and communicated with the fast reactor assembly simulation component, and is used to transport deionized water from the water tank to the fast reactor assembly simulation component;

[0086] The traffic collection module includes:

[0087] A flow meter, wherein the flow meter is provided with a flow meter solenoid valve matched therewith;

[0088] The inlet end of the flow meter is arranged to be connected to the coolant outlet of the fast reactor assembly simulation part, and the outlet end of the flow meter is arranged to be connected to the water tank. The flow meter is configured to detect the coolant flow rate flowing from the fast reactor assembly simulation part to the water tank.

[0089] In some embodiments, multiple flow meters are provided, each flow meter has a different measuring range, and each flow meter is equipped with a flow meter solenoid valve; a flow meter and a matching flow meter solenoid valve form a group of flow measurement channels; during the measurement process, the control component can automatically select the flow measurement channel that matches its measuring range for measurement according to the flow size, thereby reducing the flow measurement error and improving the measurement accuracy.

[0090] In some embodiments, the coolant flow measurement device of the sodium-cooled fast reactor assembly simulation part disclosed in the present invention comprises a data acquisition module:

[0091] Pressure collection components;

[0092] The data acquisition control component is connected to the pressure acquisition component and configured to control the pressure acquisition component to collect pressure data. The data acquisition control component is connected to the flow acquisition module and configured to control the flow acquisition module to collect coolant flow data.

[0093] Among them, the pressure collection component includes a differential pressure sensor and a matching pressure sensor solenoid valve. The high-pressure test port of the differential pressure sensor is arranged to be connected to the first pressure test hole, and the low-pressure test port of the differential pressure sensor is arranged to be connected to the second pressure test hole.

[0094] In the coolant flow measurement device of the sodium-cooled fast reactor simulation component disclosed in some embodiments, a plurality of differential pressure sensors are provided, and each differential pressure sensor has a different measurement range. Each differential pressure sensor is equipped with a pressure sensor solenoid valve; a differential pressure sensor and a pressure sensor solenoid valve matched therewith form a set of pressure drop measurement channels; during the measurement process, the control component can automatically select a pressure drop measurement channel that matches its measurement range according to the pressure drop size for measurement, thereby reducing the pressure drop measurement error and improving the measurement accuracy.

[0095] Some embodiments disclose a coolant flow measurement device for a sodium-cooled fast reactor assembly simulation component, wherein six first pressure test holes are arranged to be connected to a first connecting pipe, the first connecting pipe is sleeved outside a hexagonal outer sleeve, the first connecting pipe is arranged to be connected to a first pressure main pipe, and the first pressure main pipe is arranged to be connected to a high-pressure test port of the differential pressure sensor; six second pressure test holes are arranged to be connected to a second connecting pipe, the second connecting pipe is sleeved outside a hexagonal outer sleeve, the second connecting pipe is arranged to be connected to a second pressure main pipe, and the second pressure main pipe is arranged to be connected to a low-pressure test port of the differential pressure sensor.

[0096] In some embodiments of the coolant flow measurement device for the sodium-cooled fast reactor assembly simulation component disclosed, the first pressure test surface is closer to the fluid upstream end of the hexagonal outer sleeve, and the second pressure test surface is closer to the fluid downstream end of the hexagonal outer sleeve.

[0097] In some embodiments of the coolant flow measurement device for a sodium-cooled fast reactor assembly simulation component, a first pressure test hole is disposed in the middle of a side wall of a hexagonal outer sleeve; and a second pressure test hole is disposed in the middle of a side wall of a hexagonal outer sleeve.

[0098] In some embodiments of the coolant flow measurement device for the sodium-cooled fast reactor assembly simulation component disclosed, the distance between the first pressure test surface and the second pressure test surface is not less than two-thirds of the length of the hexagonal outer sleeve.

[0099] When the coolant flow rate is measured by using the coolant flow measurement device of the sodium-cooled fast reactor assembly simulation part, the coolant fluid flows through the hexagonal outer sleeve of the fast reactor assembly simulation part, flowing from the upstream to the downstream of the hexagonal outer sleeve. When the fluid flows in the hexagonal outer sleeve, the pressure will gradually decrease, so usually the pressure at the upstream end is generally higher than the pressure at the downstream end; the first pressure test surface is closer to the fluid upstream end of the hexagonal outer sleeve, and the first pressure test hole is arranged to be connected to the high-pressure end of the differential pressure sensor; the second pressure test surface is closer to the fluid downstream end of the hexagonal outer sleeve, and the second pressure test hole is arranged to be connected to the low-pressure end of the differential pressure sensor; generally, in order to measure the accurate pressure drop, the distance between the first pressure test surface and the second pressure test surface must meet certain conditions so that the pressure drop between the two is large enough to effectively avoid the pressure test error from having a significant impact on the pressure drop, for example, the distance between the first pressure test surface and the second pressure test surface is not less than two-thirds of the length of the hexagonal outer sleeve;

[0100] Six first pressure test holes are arranged on the six side walls corresponding to the first pressure test surface; six second pressure test holes are arranged on the six side walls corresponding to the second pressure test surface;

[0101] Usually, there are six interconnected side walls corresponding to the cross section of the hexagonal outer sleeve, and a pressure test hole is set on each side wall. The fluid pressure of the pressure test hole corresponding to each side wall is equivalent to the pressure inside the side wall;

[0102] For the first pressure test holes, the six first pressure test holes correspond to the six first pressures inside the six side walls respectively, and the six first pressure test holes are arranged to be interconnected, and are further arranged to be connected to a pressure end of the differential pressure sensor; after the six first pressure test holes are arranged to be interconnected, the six first pressures interact with each other to form a first pressure average, and a pressure test end of the differential pressure sensor obtains the first pressure average;

[0103] For the second pressure test holes, the six second pressure test holes correspond to the six second pressures inside the six side walls respectively; the six second pressure test holes are arranged to be interconnected, and are further arranged to be connected to the other pressure end of the differential pressure sensor; after the six second pressure test holes are arranged to be interconnected, the six second pressures interact with each other to form a second pressure average, and the other pressure end of the differential pressure sensor tests to obtain the second pressure average;

[0104] The pressure drop between the first pressure average and the second pressure average measured by the differential pressure sensor is positively correlated with the flow rate of the coolant fluid;

[0105] Generally, a coolant fluid with a set flow rate is used to obtain a pressure drop corresponding to the flow rate, and multiple pressure drops corresponding to multiple flow rates are obtained by using multiple coolant fluids with multiple set flow rates. Based on multiple flow rates and pressure drop data, the fluid flow rate-pressure drop relationship is processed; the fluid flow rate-pressure drop relationship can be expressed as:

[0106] ΔP=Aq 2 +Bq

[0107] Wherein, ΔP is the pressure drop between the first test surface and the second test surface, kPa; q is the coolant flow rate through the fast reactor assembly, kg / s; A and B are coefficients obtained from the experiment;

[0108] Based on the obtained fluid flow-pressure drop relationship, when a coolant fluid with a certain flow rate flows through the hexagonal outer sleeve, a corresponding pressure drop will be generated between the first pressure test surface and the second pressure test surface. According to the measured pressure drop and the obtained fluid flow-pressure drop relationship, the accurate flow rate of the coolant fluid can be obtained.

[0109] The technical details are further illustrated below in conjunction with embodiments.

[0110] Example 1

[0111] Figure 1 This is a schematic diagram of coolant flow measurement of a sodium-cooled fast reactor assembly simulation component disclosed in Example 1. Figure 2 This is a schematic diagram of the test structure setting for the first pressure test surface. Figure 3 This is a schematic diagram of the test structure setting for the second pressure test surface. Figure 4 Setting a top view for the first pressure test surface structure;

[0112] The fast reactor assembly simulation comprises an operating head 1, an upper transition joint 2, a hexagonal outer sleeve 3, a lower transition joint 4 and a tube pin 5 which are arranged in sequence; wherein the operating head 1 is arranged to be connected with the upper transition joint 2; the upper transition joint 2 is arranged to be communicated with the outlet end of the hexagonal outer sleeve 3, an assembly rod cluster 10 is arranged in the hexagonal outer sleeve 3, and the assembly rod cluster 10 is fixedly mounted on the support frame of the upper transition joint 2 and the support frame of the lower transition joint 4; the cavity between the inner wall of the hexagonal outer sleeve 3 and the assembly rod cluster 10 forms a coolant flow area in the fast reactor assembly simulation; the inlet end of the hexagonal outer sleeve 3 is arranged to be communicated with the lower transition joint 4; the tube pin 5 is arranged to be connected with the lower part of the lower transition joint 4;

[0113] Under the out-of-pile hydraulic test conditions, the coolant deionized water enters from the coolant inlet on the pin 5, passes through the lower transition joint 4, the hexagonal outer sleeve 3 and the upper transition joint 2, and finally flows out from the coolant outlet of the operating head 1; Figure 1 The arrow in the middle shows the direction of coolant flow;

[0114] The process of measuring the coolant flow rate of the fast reactor assembly simulation includes:

[0115] Two cross sections at different positions are arranged in the axial direction of the hexagonal outer sleeve 3 as a first pressure test surface 6 and a second pressure test surface 7;

[0116] A first pressure test hole 61 is respectively arranged on the six side walls corresponding to the first pressure test surface 6; the six first pressure test holes 61 are respectively arranged to be connected to the first pressure test tubes 62, and the six first pressure test tubes 62 are arranged to be connected to the first connecting tube 63, and the first connecting tube 63 forms a hexagonal annular tube arranged outside the hexagonal outer sleeve 3, and the first connecting tube 63 is provided with a first pressure main pipe 64 in communication; the six first pressure test tubes 62, the first connecting tube 63 and the first pressure main pipe 64 form a seven-way connection structure to ensure that the first pressure main pipe 64 is connected to the six first pressure test tubes 62 in real time, and the pressure of the first pressure test tubes 62 is merged; wherein, the first pressure test hole can be a static pressure measurement hole with a diameter of 2 mm opened on the side wall of the hexagonal outer sleeve 3, and the first pressure test tube and the first pressure main pipe can be stainless steel tubes with an inner diameter of 2 mm and an outer diameter of 3 mm;

[0117] A second pressure test hole 71 is respectively arranged on the six side walls corresponding to the second pressure test surface 7; the six second pressure test holes 71 are respectively arranged to be connected to the second pressure test tubes 72, the six second pressure test tubes 72 are arranged to be connected to the second connecting tube 73, the second connecting tube 73 forms a hexagonal ring tube arranged outside the hexagonal outer sleeve 3, and the second connecting tube 73 is provided with a second pressure main pipe 74; the six second pressure test tubes 72, the second connecting tubes 73 and the second pressure main pipe 74 form a seven-way connection structure to ensure that the second pressure main pipe 74 is connected to the six second pressure test tubes 72 in real time, and the pressure of the second pressure test tubes 72 is merged; wherein, the second pressure test hole can be a static pressure measurement hole with a diameter of 2 mm opened on the side wall of the hexagonal outer sleeve 3, and the second pressure test tube and the second pressure main pipe can be stainless steel pipes with an inner diameter of 2 mm and an outer diameter of 3 mm;

[0118] The first pressure main pipe 64 and the second pressure main pipe 74 are respectively connected to the high pressure test interface and the low pressure test interface of the differential pressure sensor 8;

[0119] When a coolant fluid flows through the hexagonal outer sleeve 3, the differential pressure sensor 8 detects the pressure drop between the first test surface 6 and the second test surface 7;

[0120] Different flow rates are set for pressure drop detection, and the pressure drops at different flow rates are measured; based on multiple flow rate data and corresponding pressure drop data, the fluid flow rate-pressure drop relationship is processed; the fluid flow rate-pressure drop relationship can be expressed as:

[0121] ΔP=Aq2 +Bq

[0122] Wherein, ΔP is the pressure drop between the first test surface and the second test surface, kPa; q is the coolant flow rate through the fast reactor assembly, kg / s; A and B are coefficients obtained from the experiment;

[0123] When a coolant fluid with a certain flow rate flows through the hexagonal outer sleeve of the fast reactor assembly, a corresponding pressure drop will be generated between the first pressure test surface and the second pressure test surface. The accurate flow rate of the coolant fluid can be obtained based on the measured pressure drop and the fluid flow-pressure drop relationship.

[0124] Example 2

[0125] Example 2 discloses a coolant flow measurement device for a sodium-cooled fast reactor assembly simulation component; Figure 5 As shown, the measuring device comprises:

[0126] The fast reactor assembly simulation experiment module 100 is used to simulate the flow measurement conditions of the fast reactor assembly simulation parts;

[0127] The coolant circulation module 200 is connected to the fast reactor assembly simulation experiment module 100 and is used to provide the fast reactor assembly simulation experiment module 100 with coolant that meets the set conditions;

[0128] The flow collection module 400 is arranged to be connected to the fast reactor assembly simulation experiment module 100 and the coolant circulation module 200, respectively, and is used to measure the coolant flow flowing through the fast reactor assembly simulation experiment module 100;

[0129] The data acquisition module 300 is respectively connected to the flow acquisition module 300 and the fast reactor component simulation experiment module 100, and is used to collect and process data;

[0130] The fast reactor assembly simulation experiment module 100 includes: a fast reactor assembly simulation part 103, a simulation part bottom support structure 101 arranged and installed at the bottom of the fast reactor assembly simulation part 103, and a simulation part top support structure 102 arranged and installed at the top of the fast reactor assembly simulation part 103; the simulation part bottom support structure 101 and the simulation part top support structure 102 stabilize the fast reactor assembly simulation part 103 at a set position to form the fast reactor assembly simulation experiment module 100;

[0131] The fast reactor assembly simulation part 103 includes an operating head, an upper transition joint, a hexagonal outer sleeve, a lower transition joint and a tube pin which are arranged in sequence. The operating head is adapted to be arranged in the top support structure 102 of the simulation part, and the tube pin is adapted to be arranged and fixed in the bottom support structure 101 of the simulation part.

[0132] The hexagonal outer sleeve of the fast reactor assembly simulation part 103 is respectively provided with a first pressure test surface 6 and a second pressure test surface 7; the six corresponding first pressure test holes on the first pressure test surface 6 are arranged to be connected to the first pressure main pipe; the six corresponding second pressure test holes on the second pressure test surface 7 are arranged to be connected to the second pressure main pipe;

[0133] The coolant circulation module 200 includes: a water tank 203 for storing coolant deionized water; a water level gauge 202 is provided in the water tank 203, a heating pipe 205 is provided at the bottom of the water tank 203 for heating the deionized water in the water tank 203, and the heating pipe 205 is provided with a temperature adjustment control component 206 for controlling the heating pipe 205 to heat the deionized water; a deionized water production component 207 is provided to be connected with the water tank 203, and is used to generate deionized water and transport it into the water tank 203; a water level control component 201 is provided to be connected with the water level gauge 202 and the deionized water production component 207, and is used to control the water level of the deionized water in the water tank 203; the water tank 203 is provided with a circulating water pump 204, and the circulating water pump 204 is further provided to be connected with the fast reactor assembly simulation experiment module 100, and is used to transport the deionized water to the fast reactor assembly simulation part 103;

[0134] The flow acquisition module 400 includes a flow meter 402, and the flow meter 402 is provided with a flow meter solenoid valve 401 provided therewith; the inlet end of the flow meter 402 is provided to be connected with the coolant outlet of the fast reactor assembly simulation experiment module 100, and the outlet end of the flow meter 402 is provided to be connected with the water tank 203, and the flow meter 402 is configured to detect the coolant flow rate flowing from the fast reactor assembly simulation experiment module 100 to the water tank 203; the flow meter 402 may be a high-precision electromagnetic flow meter, and the measurement accuracy is 0.3% MV;

[0135] The data acquisition module 300 includes a data acquisition control component 301 and a pressure acquisition component 302, wherein the data acquisition control component 301 is connected to the pressure acquisition component 302 and configured to control the pressure acquisition component 302 to acquire pressure data, and the data acquisition control component 301 is connected to the flow acquisition module 400 and configured to control the flow acquisition module 400 to acquire coolant flow data;

[0136] The pressure acquisition component 302 includes a differential pressure sensor 3022 and a pressure sensor solenoid valve 3021 matched therewith; the high pressure test port of the differential pressure sensor 3022 is arranged to be connected to the first pressure main pipe corresponding to the first pressure test surface 6, and the low pressure test port of the differential pressure sensor 3022 is arranged to be connected to the second pressure main pipe corresponding to the second pressure test surface 7; the differential pressure sensor 3022 can be a high-precision differential pressure sensor with a measurement accuracy of 0.15% FS;

[0137] When the coolant flow measurement device for the sodium-cooled fast reactor assembly simulation part disclosed in Example 2 is used to measure the flow, under the out-of-pile hydraulic test conditions, the coolant deionized water enters from the coolant inlet on the pin 5, passes through the lower transition joint 4, the hexagonal outer sleeve 3 and the upper transition joint 2, and finally flows out from the coolant outlet of the operating head 1;

[0138] The temperature regulating control component 206 of the coolant circulation module 200 controls the heating tube 205 to heat the deionized water to the set temperature, and the water pump 204 delivers the deionized water of the set flow rate to the fast reactor assembly simulation experiment module 100, and enters the interior of the hexagonal outer sleeve 3 from the coolant inlet of the pin 5, flows through the first pressure test surface 6 and the second pressure test surface 7 in sequence, and then flows out from the coolant outlet of the operating head 1, wherein the pressure difference sensor 3022 of the pressure acquisition component 302 detects the pressure difference between the two pressure test surfaces, and the flow meter 402 of the flow acquisition module 400 detects the actual flow rate of the deionized water; the data acquisition control component 301 collects and processes data;

[0139] Based on the hydraulic characteristics test data, the flow-pressure drop relationship of the fast reactor component simulation under full flow conditions can be determined; generally, the full flow condition selects a rated flow range of 20-110%;

[0140] Generally, the flow-pressure drop relationship obtained from the hydraulic characteristic test is embedded in the data acquisition control module through computer programming, and the pressure drop value between the first pressure test surface and the second pressure test surface of the component simulation part is measured through the data acquisition control module 300. The flow-pressure drop relationship can be used to calculate and display the coolant flow through the sodium-cooled component simulation part in real time; the coolant flow measurement accuracy is not less than 1%.

[0141] The coolant flow measurement device of a sodium-cooled fast reactor assembly simulation component disclosed in an embodiment of the present invention has two pressure test surfaces at two different axial positions of a hexagonal outer sleeve of the fast reactor assembly simulation component, and further has a pressure test hole respectively arranged on the six side surfaces of the hexagonal outer sleeve. The flow rate of the coolant fluid is accurately obtained by measuring the pressure drop by utilizing the relationship between the pressure drop and the flow rate formed between the two force test surfaces when the coolant fluid flows through the hexagonal outer sleeve. The disturbance to the flow field is small and the measurement accuracy is high. The device can provide reliable technical support for an off-core hydraulic test of a sodium-cooled fast reactor core flow distribution, and has good application prospects in the coolant flow measurement of a sodium-cooled fast reactor assembly simulation component.

[0142] The technical solutions disclosed in the embodiments of the present invention and the technical details disclosed in the embodiments are merely illustrative of the inventive concept of the present invention and do not constitute a limitation on the technical solutions of the embodiments of the present invention. Any conventional changes, replacements or combinations of the technical details disclosed in the embodiments of the present invention have the same inventive concept as the present invention and are within the protection scope of the claims of the present invention.

Claims

1. A coolant flow measurement device for a sodium-cooled fast reactor assembly simulation, characterized in that: The measuring device comprises: Fast reactor assembly simulation experiment module, used to simulate the flow measurement conditions of fast reactor assembly simulation parts; A coolant circulation module is provided, connected to the fast reactor assembly simulation experiment module, and is used to provide coolant meeting set conditions to the fast reactor assembly simulation experiment module; a flow collection module, arranged to be in communication with the fast reactor assembly simulation experiment module and the coolant circulation module, respectively, and used to measure the coolant flow rate flowing through the fast reactor assembly simulation experiment module; A data acquisition module, arranged to be connected to the flow acquisition module and the fast reactor component simulation experiment module respectively, for collecting and processing data; The fast reactor assembly simulation experiment module includes: A fast reactor assembly simulation part, comprising an operating head, an upper transition joint, a hexagonal outer sleeve, a lower transition joint and a tube pin that are arranged to be connected in sequence; A dummy bottom support structure is arranged at the bottom of the fast reactor assembly dummy and is adapted to be installed and fixed with the tube pins; A simulation component top support structure is arranged on the top of the fast reactor assembly simulation component and is adapted to be installed and fixed with the operating head; Two cross sections at different positions are arranged in the axial direction of the hexagonal outer sleeve as a first pressure test surface and a second pressure test surface; A first pressure test hole is respectively arranged on the six side walls of the hexagonal outer sleeve corresponding to the first pressure test surface; the six first pressure test holes are arranged to be interconnected, and are further arranged to be connected to a data acquisition module; A second pressure test hole is respectively arranged on the six side walls of the hexagonal outer sleeve corresponding to the second pressure test surface; the six second pressure test holes are arranged to be interconnected, and are further arranged to be connected to a data acquisition module; the data acquisition module is configured to detect the pressure drop between the first pressure test surface and the second test surface, and obtain the coolant flow rate based on the pressure drop calculation.

2. The coolant flow measurement device for a sodium-cooled fast reactor assembly simulation according to claim 1, characterized in that: The coolant circulation module comprises: A water tank is used to store coolant deionized water; a water level gauge is provided in the water tank, and a heating pipe is provided at the bottom of the water tank to heat the deionized water in the water tank; A temperature adjustment control component, arranged to be connected to the heating tube and used to control the heating tube; A deionized water production component, arranged to be in communication with the water tank, for generating deionized water and delivering it to the water tank; A water level control component, connected to the water level gauge and the deionized water production component, for controlling the deionized water level in the water tank; A circulating water pump is arranged to be connected to the water tank. The circulating water pump is arranged to be in communication with the fast reactor assembly simulation component and is used to transport deionized water from the water tank to the fast reactor assembly simulation component.

3. The coolant flow measurement device for a sodium-cooled fast reactor assembly simulation according to claim 2, characterized in that: The flow collection module includes: A flow meter, wherein the flow meter is provided with a flow meter solenoid valve matched therewith; The inlet end of the flow meter is arranged to communicate with the coolant outlet of the fast reactor assembly simulation component, and the outlet end of the flow meter is arranged to communicate with the water tank. The flow meter is configured to detect the coolant flow rate flowing from the fast reactor assembly simulation component to the water tank.

4. The coolant flow measurement device for a sodium-cooled fast reactor assembly simulation according to claim 3, characterized in that: There are multiple flow meters, and each of the flow meters has a different measurement range.

5. The coolant flow measurement device for a sodium-cooled fast reactor assembly simulation according to claim 3, characterized in that: The data acquisition module comprises: Pressure collection components; A data acquisition control component; the data acquisition control component is connected to the pressure acquisition component and configured to control the pressure acquisition component to collect pressure data; the data acquisition control component is connected to the flow acquisition module and configured to control the flow acquisition module to collect coolant flow data; Among them, the pressure collection component includes a differential pressure sensor and a pressure sensor solenoid valve matched therewith, the high pressure test port of the differential pressure sensor is arranged to be connected to the first pressure test hole, and the low pressure test port of the differential pressure sensor is arranged to be connected to the second pressure test hole.

6. The coolant flow measurement device for a sodium-cooled fast reactor assembly simulation according to claim 5, characterized in that: A plurality of differential pressure sensors are provided, and each of the differential pressure sensors has a different measurement range.

7. The coolant flow measurement device for a sodium-cooled fast reactor assembly simulation according to claim 5, characterized in that: The six first pressure test holes are arranged to be connected to a first connecting pipe, the first connecting pipe is sleeved outside the hexagonal outer sleeve, the first connecting pipe is arranged to be connected to a first pressure main pipe, and the first pressure main pipe is arranged to be connected to a high pressure test port of the differential pressure sensor; The six second pressure test holes are arranged to be connected to the second connecting pipe, the second connecting pipe is sleeved outside the hexagonal outer sleeve, the second connecting pipe is arranged to be connected to the second pressure main pipe, and the second pressure main pipe is arranged to be connected to the low pressure test port of the differential pressure sensor.

8. The coolant flow measurement device for a sodium-cooled fast reactor assembly simulation according to claim 1, characterized in that: The first pressure test surface is closer to the fluid upstream end of the hexagonal outer sleeve, and the second pressure test surface is closer to the fluid downstream end of the hexagonal outer sleeve.

9. The coolant flow measurement device for a sodium-cooled fast reactor assembly simulation according to claim 1, characterized in that: The first pressure testing hole is arranged at the middle position of the side wall; the second pressure testing hole is arranged at the middle position of the side wall.

10. The coolant flow measurement device for a sodium-cooled fast reactor assembly simulation according to claim 1, characterized in that: The distance between the first pressure test surface and the second pressure test surface is not less than two-thirds of the length of the hexagonal outer sleeve.

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