Cooling liquid flow measuring method for sodium-cooled fast reactor assembly simulation part

Abstract

The embodiment of the invention discloses a cooling liquid flow measuring method for a sodium-cooled fast reactor assembly simulation part. The cooling liquid flow measuring method comprises the steps that two cross sections with different positions are arranged in the axial direction of a hexagonal outer sleeve of the sodium-cooled fast reactor assembly simulation part to serve as a first pressure testing face and a second pressure testing face; six first pressure test points are arranged on six side walls corresponding to the first pressure test surface; six second pressure test points are arranged on six side walls corresponding to the second pressure test surface; the six first pressure test points are communicated with one another and are further connected with one pressure end of the differential pressure sensor; the six second pressure test points are communicated with one another and are further connected with the other pressure end of the differential pressure sensor; when cooling liquid flows through the hexagonal outer sleeve, the pressure difference sensor detects the pressure drop between the first test surface and the second test surface; and on the basis of the fluid flow-pressure drop relation, the flow of the cooling liquid is obtained according to the measured pressure drop.

Description

Technical Field

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

[0002] The sodium-cooled fast reactor is a type of advanced nuclear power reactor of the fourth generation under development in my country. The pool-type primary cooling system mainly includes key components such as sodium pumps, large grid plate headers, small grid plate headers and in-core components. After the cooling sodium liquid is distributed through the large grid plate headers and small grid plate headers, it enters the components through the tube pin openings and takes away the heat generated by the fuel rod bundle 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. The sodium-cooled fast reactor components 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 rate 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 outer 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 method for measuring the coolant flow rate of a sodium-cooled fast reactor assembly simulation part, wherein the sodium-cooled fast reactor assembly simulation part includes an assembly rod bundle, and the components of the assembly rod bundle are arranged in a hexagonal outer sleeve; the measurement method includes:

[0006] 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;

[0007] Six first pressure test points are set on the six side walls corresponding to the first pressure test surface; six second pressure test points are set on the six side walls corresponding to the second pressure test surface;

[0008] The six first pressure test points are arranged to be interconnected, and are further arranged to be connected to a pressure end of a differential pressure sensor;

[0009] The six second pressure test points are arranged to be interconnected, and are further arranged to be connected to another pressure end of the differential pressure sensor;

[0010] When a coolant fluid flows through the hexagonal outer sleeve, the differential pressure sensor detects a pressure drop between the first test surface and the second test surface;

[0011] Based on the fluid flow-pressure drop relationship, the flow rate of the coolant fluid is obtained according to the measured pressure drop.

[0012] Further, some embodiments disclose a method for measuring coolant flow rate of a sodium-cooled fast reactor assembly simulator, comprising the step of determining a fluid flow rate-pressure drop relationship, specifically comprising:

[0013] Using a coolant fluid with a set flow rate, a pressure drop corresponding to the flow rate is obtained;

[0014] Using a plurality of coolant fluids with set flow rates, a plurality of pressure drops corresponding to the plurality of flow rates are obtained;

[0015] Based on a plurality of flow rate and pressure drop data, a fluid flow rate-pressure drop relationship is obtained through processing.

[0016] In some embodiments of the present invention, the coolant flow measurement method of the sodium-cooled fast reactor assembly simulation component is disclosed, and the fluid flow-pressure drop relationship is expressed as:

[0017] ΔP=Aq 2 +Bq

[0018] 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 sodium-cooled fast reactor assembly simulation, kg / s; A and B are coefficients obtained from the experiment.

[0019] In some embodiments of the method for measuring coolant flow of a sodium-cooled fast reactor assembly simulation component, 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.

[0020] Some embodiments disclose a method for measuring coolant flow of a sodium-cooled fast reactor assembly simulation component, wherein a first pressure test surface is closer to the fluid upstream end of a hexagonal outer sleeve, and a first pressure test point is arranged to be connected to a high-pressure end of a differential pressure sensor; a second pressure test surface is closer to the fluid downstream end of a hexagonal outer sleeve, and a second pressure test point is arranged to be connected to a low-pressure end of the differential pressure sensor.

[0021] In some embodiments of the coolant flow measurement method for a sodium-cooled fast reactor assembly simulation component, a first pressure test point is set at a middle position of a side wall; and a second pressure test point is set at a middle position of a side wall.

[0022] Some embodiments disclose a method for measuring the coolant flow rate of a sodium-cooled fast reactor assembly simulation component, wherein six first pressure test points are arranged to be connected to a first connecting tube, the first connecting tube is sleeved outside a hexagonal outer sleeve, and the first connecting tube is arranged to be connected to one pressure end of a differential pressure sensor; six second pressure test points are arranged to be connected to a second connecting tube, the second connecting tube is sleeved outside a hexagonal outer sleeve, and the second connecting tube is arranged to be connected to the other pressure end of the differential pressure sensor.

[0023] Some embodiments disclose a method for measuring coolant flow of a sodium-cooled fast reactor assembly simulation component, wherein the sodium-cooled fast reactor assembly simulation component further includes an operating head, an upper transition joint, a lower transition joint, and a pin; wherein,

[0024] The operating head is connected to the upper transition joint; the operating head is provided with a coolant outlet;

[0025] The upper transition joint is arranged to be in communication with the outlet end of the hexagonal outer sleeve;

[0026] The upper part of the lower transition joint is arranged to be connected with the inlet end of the hexagonal outer sleeve; the two ends of the assembly rod bundle arranged in the hexagonal outer sleeve are respectively fixedly mounted on the support frame of the upper transition joint and the support frame of the lower transition joint; the cavity between the inner wall of the hexagonal outer sleeve and the assembly rod bundle forms a coolant flow area in the fast reactor assembly simulation part;

[0027] The lower part of the lower transition joint is connected to the tube pin; the tube pin is provided with a coolant inlet.

[0028] The coolant flow measurement method of a sodium-cooled fast reactor component simulation part disclosed in an embodiment of the present invention comprises two pressure test surfaces at two different axial positions of a hexagonal outer sleeve of an in-core component, and further a pressure test point is respectively set on six side surfaces of the hexagonal outer sleeve. 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 is utilized, and the flow rate of the coolant fluid is accurately obtained by measuring the pressure drop. The method has small disturbance to the flow field and high measurement accuracy, and 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 component simulation part. BRIEF DESCRIPTION OF THE DRAWINGS

[0029] Figure 1 A schematic diagram of a coolant flow measurement method for a sodium-cooled fast reactor assembly simulation component disclosed in Example 1;

[0030] Figure 2 A schematic diagram of the test structure setting of the first pressure test surface disclosed in Example 1;

[0031] Figure 3 A schematic diagram of the test structure setting of the second pressure test surface disclosed in Example 1;

[0032] Figure 4 A top view of the first pressure test surface structure disclosed in Example 1;

[0033] Figure 5 This is a schematic diagram of the coolant flow testing device disclosed in Example 2.

[0034] Reference numerals

[0035] 1 Operating head 2 Upper transition joint

[0036] 3 Hexagonal outer sleeve 4 Lower transition joint

[0037] 5 Pin 6 First pressure test surface

[0038] 7 Second pressure test surface 8 Differential pressure sensor

[0039] 61 First pressure test point 62 First pressure test tube

[0040] 63 First connecting pipe 64 First pressure main pipe

[0041] 71 Second pressure test point 72 Second pressure test tube

[0042] 73 Second connecting pipe 74 Second pressure main pipe

[0043] 10 Component rod cluster 100 Fast reactor component simulation test module

[0044] 200 Coolant circulation module 300 Data acquisition module

[0045] 400 Flow collection module 101 Simulation bottom support structure

[0046] 102 Simulation top support structure 201 Water level control component

[0047] 202 Water level gauge 203 Water tank

[0048] 204 Circulating water pump 205 Heating pipe

[0049] 206 Water temperature regulation and control component 207 Deionized water production component

[0050] 301 Data acquisition control component 302 Pressure acquisition component

[0051] 3021 Pressure sensor solenoid valve 3022 Differential pressure sensor

[0052] 401 Flow meter solenoid valve 402 Flow meter

[0053] 10 Component rod bundle 103 Sodium-cooled fast reactor component simulation DETAILED DESCRIPTION

[0054] 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.

[0055] 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.

[0056] 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.

[0057] 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.

[0058] 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.

[0059] 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.

[0060] In some embodiments, a sodium-cooled fast reactor assembly simulator includes an assembly rod bundle, and components of the assembly rod bundle are disposed in a hexagonal outer sleeve;

[0061] In some embodiments, the sodium-cooled fast reactor assembly simulation 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: wherein the operating head is arranged in connection with the upper transition joint, and is used for loading and unloading the fast reactor assembly simulation on the one hand, and serves as a coolant outlet of the fast reactor assembly simulation on the other hand; a positioning block is arranged on the outer side of the upper transition joint to ensure 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-pile 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;

[0062] The coolant flow measurement method of the sodium-cooled fast reactor assembly simulation includes:

[0063] 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;

[0064] Generally, when the coolant fluid flows through the sodium-cooled fast reactor assembly simulation part, it flows 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 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 upstream end of the fluid of the hexagonal outer sleeve, and the first pressure test point is connected to the high-pressure end of the differential pressure sensor; the second pressure test surface is closer to the downstream end of the fluid of the hexagonal outer sleeve, and the second pressure test point is 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;

[0065] Six first pressure test points are set on the six side walls corresponding to the first pressure test surface; six second pressure test points are set on the six side walls corresponding to the second pressure test surface;

[0066] Usually, there are six interconnected side walls corresponding to the cross section of the hexagonal outer sleeve, and a pressure test point is set on each side wall. The fluid pressure of the pressure test point corresponding to each side wall is equivalent to the pressure inside the side wall; for the first pressure test point, the six first pressure test points correspond to the six first pressures inside the six side walls respectively, and for the second pressure test point, the six second pressure test points correspond to the six second pressures inside the six side walls respectively;

[0067] Generally, the first pressure test point arranged on the side wall of the hexagonal outer sleeve is located at the middle of the side wall; the second pressure test point is located at the middle of the side wall;

[0068] The six first pressure test points 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 points are arranged to be interconnected, the six first pressures interact with each other to form a first pressure average, which acts on a pressure test end of the differential pressure sensor;

[0069] The six second pressure test points are arranged to be interconnected, and are further arranged to be connected to another pressure end of the differential pressure sensor; after the six second pressure test points are arranged to be interconnected, the six second pressures interact with each other to form a second pressure average, which acts on the other pressure end of the differential pressure sensor;

[0070] When a coolant fluid flows through the hexagonal outer sleeve, the differential pressure sensor detects a pressure drop between a first pressure average value of the first test surface and a second pressure average value of the second test surface;

[0071] 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:

[0072] ΔP=Aq 2 +Bq

[0073] 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 sodium-cooled fast reactor assembly simulation, kg / s, and A and B are coefficients obtained from the experiment;

[0074] Based on the obtained fluid flow-pressure drop relationship, when a coolant fluid with a certain flow rate flows through the hexagonal outer sleeve of the sodium-cooled fast reactor assembly simulation, 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.

[0075] Some embodiments disclose a method for measuring the coolant flow rate of a sodium-cooled fast reactor assembly simulation component, wherein six first pressure test points are arranged to be connected to a first connecting tube, the first connecting tube is sleeved outside a hexagonal outer sleeve, and the first connecting tube is arranged to be connected to one pressure end of a differential pressure sensor; six second pressure test points are arranged to be connected to a second connecting tube, the second connecting tube is sleeved outside a hexagonal outer sleeve, and the second connecting tube is arranged to be connected to the other pressure end of the differential pressure sensor.

[0076] The technical details are further illustrated below in conjunction with embodiments.

[0077] Example 1

[0078] Figure 1 Schematic diagram of the coolant flow measurement method of the 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;

[0079] The sodium-cooled 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;

[0080] 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;

[0081] The coolant flow measurement method of the sodium-cooled fast reactor assembly simulation includes:

[0082] 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;

[0083] A first pressure test point 61 is respectively arranged on the six side walls corresponding to the first pressure test surface 6; the six first pressure test points 61 are respectively arranged to be connected to the first pressure test tubes 62, the six first pressure test tubes 62 are arranged to be connected to the first connecting tube 63, the first connecting tube 63 forms a hexagonal ring tube arranged outside the hexagonal outer sleeve 3, and the first connecting tube 63 is provided with a first pressure main pipe 64; 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 point 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;

[0084] A second pressure test point 71 is respectively arranged on the six side walls corresponding to the second pressure test surface 7; the six second pressure test points 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 point 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;

[0085] 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;

[0086] 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;

[0087] 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:

[0088] ΔP=Aq 2 +Bq

[0089] 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 sodium-cooled fast reactor assembly simulation, kg / s; A and B are coefficients obtained from the experiment;

[0090] When a coolant fluid with a certain flow rate flows through the hexagonal outer sleeve of the sodium-cooled fast reactor assembly simulation component, 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 obtained fluid flow-pressure drop relationship;

[0091] Generally, a computer program is compiled to embed the flow-pressure difference relationship of the component simulation obtained from the hydraulic characteristic test into a data acquisition and conversion system. The pressure drop value between the first pressure test surface and the second pressure test surface of the component simulation is measured through the data acquisition and conversion system. The compiled flow-pressure drop relationship can be used to calculate and display the coolant flow through the component simulation in real time.

[0092] Example 2

[0093] Example 2 discloses a measurement system for a method for measuring coolant flow rate of a sodium-cooled fast reactor assembly simulation component; Figure 5 As shown, the measurement system includes:

[0094] The fast reactor assembly simulation experiment module 100 is used to simulate the flow measurement conditions of the fast reactor assembly simulation parts;

[0095] A coolant circulation module 200 is provided to be connected to the fast reactor assembly simulation experiment module 100, and is used to provide coolant meeting set conditions to the fast reactor assembly simulation experiment module 100;

[0096] A flow collection module 400 is provided 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 rate flowing through the fast reactor assembly simulation experiment module 100;

[0097] A data acquisition module 300 is provided to be connected to the flow acquisition module 300 and the fast reactor assembly simulation experiment module 100, respectively, and is used to collect and process data;

[0098] The fast reactor assembly simulation experiment module 100 includes: a sodium-cooled fast reactor assembly simulation part 103, a simulation part bottom support structure 101 arranged and installed at the bottom of the sodium-cooled fast reactor assembly simulation part 103, and a simulation part top support structure 102 arranged and installed at the top of the sodium-cooled fast reactor assembly simulation part 103; the simulation part bottom support structure 101 and the simulation part top support structure 102 stabilize the sodium-cooled fast reactor assembly simulation part 103 at a set position to form the fast reactor assembly simulation experiment module 100;

[0099] The sodium-cooled 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.

[0100] The hexagonal outer sleeve of the sodium-cooled 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 points on the first pressure test surface 6 are arranged to be connected to the first pressure main pipe; the six corresponding second pressure test points on the second pressure test surface 7 are arranged to be connected to the second pressure main pipe;

[0101] The coolant circulation module 200 includes: a water tank 203 for storing coolant deionized water; a water level gauge 202 is arranged in the water tank 203, a heating pipe 205 is arranged at the bottom of the water tank 203 for heating the deionized water in the water tank 203, and the heating pipe 205 is connected 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 arranged 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 arranged 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 arranged to be connected with a circulating water pump 204, and the circulating water pump 204 is further arranged to be connected with the fast reactor assembly simulation experiment module 100, and is used to transport the deionized water to the sodium-cooled fast reactor assembly simulation part 103;

[0102] 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;

[0103] 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;

[0104] 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;

[0105] When the coolant flow measurement system for the sodium-cooled fast reactor assembly simulation disclosed in Example 2 is used to measure the flow, under the conditions of the out-of-pile hydraulic test, 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;

[0106] 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;

[0107] Based on the hydraulic characteristics test data, the flow-pressure drop relationship of the sodium-cooled fast reactor component simulation under full flow conditions can be determined; generally, the full flow condition selects a rated flow range of 20-110%;

[0108] Generally, the flow-pressure difference 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%.

[0109] The method for measuring the coolant flow rate of a sodium-cooled fast reactor assembly simulation component disclosed in an embodiment of the present invention comprises the following steps: setting two pressure test surfaces at two different axial positions of a hexagonal outer sleeve of the sodium-cooled fast reactor assembly simulation component, and further setting a pressure test point on each of the six side surfaces of the hexagonal outer sleeve. 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 is utilized, and the flow rate of the coolant fluid is accurately obtained by measuring the pressure drop. The method has small disturbance to the flow field and high measurement accuracy, and can provide reliable technical support for an off-core hydraulic test of a sodium-cooled fast reactor core flow distribution. The method has good application prospects in the measurement of the coolant flow rate of a sodium-cooled fast reactor assembly simulation component.

[0110] 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 method for measuring coolant flow rate of a sodium-cooled fast reactor assembly simulation component, characterized in that: The sodium-cooled fast reactor assembly simulation comprises an assembly rod bundle, and components of the assembly rod bundle are arranged in a hexagonal outer sleeve; The measuring method comprises: 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; Six first pressure test points are set on the six side walls corresponding to the first pressure test surface; six second pressure test points are set on the six side walls corresponding to the second pressure test surface; The six first pressure test points are arranged to be interconnected, and are further arranged to be connected to a pressure end of a differential pressure sensor; The six second pressure test points are arranged to be interconnected, and further arranged to be connected to another pressure end of the differential pressure sensor; When a coolant fluid flows through the hexagonal outer sleeve, the differential pressure sensor detects a pressure drop between the first test surface and the second test surface; Based on the fluid flow-pressure drop relationship, the flow rate of the coolant fluid is obtained according to the measured pressure drop.

2. The method for measuring coolant flow rate of a sodium-cooled fast reactor assembly simulation according to claim 1, characterized in that: The step of determining the fluid flow-pressure drop relationship includes: Using a coolant fluid with a set flow rate, a pressure drop corresponding to the flow rate is obtained; Using a plurality of coolant fluids with set flow rates, a plurality of pressure drops corresponding to the plurality of flow rates are obtained; Based on a plurality of flow rate and pressure drop data, a fluid flow rate-pressure drop relationship is obtained through processing.

3. The method for measuring coolant flow rate of a sodium-cooled fast reactor assembly simulation according to claim 2, characterized in that: The fluid flow-pressure drop relationship is expressed as: ΔP=Aq 2 +Bq 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 sodium-cooled fast reactor assembly simulation, kg / s; A and B are coefficients obtained from the experiment.

4. According to the coolant flow measurement method of the sodium-cooled fast reactor assembly simulation part, it is 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.

5. The method for measuring coolant flow rate of 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 first pressure test point 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 point is arranged to be connected to the low-pressure end of the differential pressure sensor.

6. The method for measuring coolant flow rate of a sodium-cooled fast reactor assembly simulation according to claim 1, characterized in that: The first pressure test point is set at the middle position of the side wall; the second pressure test point is set at the middle position of the side wall.

7. The method for measuring coolant flow rate of a sodium-cooled fast reactor assembly simulation according to claim 1, characterized in that: The six first pressure test points are arranged to be connected to the first connecting pipe, the first connecting pipe is sleeved outside the hexagonal outer sleeve, and the first connecting pipe is arranged to be connected to one pressure end of the differential pressure sensor; the six second pressure test points are arranged to be connected to the second connecting pipe, the second connecting pipe is sleeved outside the hexagonal outer sleeve, and the second connecting pipe is arranged to be connected to the other pressure end of the differential pressure sensor.

8. The method for measuring coolant flow rate of a sodium-cooled fast reactor assembly simulation component according to claim 1, characterized in that: The sodium-cooled fast reactor assembly simulation also includes an operating head, an upper transition joint, a lower transition joint and a tube pin; wherein, The operating head is connected to the upper transition joint; the operating head is provided with a coolant outlet; The upper transition joint is arranged to communicate with the outlet end of the hexagonal outer sleeve; The upper part of the lower transition joint is arranged to communicate with the inlet end of the hexagonal outer sleeve; the two ends of the assembly rod bundle arranged in the hexagonal outer sleeve are respectively fixedly mounted on the support frame of the upper transition joint and the support frame of the lower transition joint; the cavity between the inner wall of the hexagonal outer sleeve and the assembly rod bundle forms a coolant flow area in the fast reactor assembly simulation part; The lower part of the lower transition joint is connected to the tube pin; the tube pin is provided with a coolant inlet.

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