CN110598316B - Construction of digital prototype method of shielded nuclear main pump based on beam finite element model - Google Patents
Construction of digital prototype method of shielded nuclear main pump based on beam finite element model Download PDFInfo
- Publication number
- CN110598316B CN110598316B CN201910854567.8A CN201910854567A CN110598316B CN 110598316 B CN110598316 B CN 110598316B CN 201910854567 A CN201910854567 A CN 201910854567A CN 110598316 B CN110598316 B CN 110598316B
- Authority
- CN
- China
- Prior art keywords
- main pump
- nuclear main
- finite element
- model
- pump
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Active
Links
- 238000000034 method Methods 0.000 title claims abstract description 27
- 238000010276 construction Methods 0.000 title abstract description 3
- 238000004458 analytical method Methods 0.000 claims abstract description 76
- 238000004088 simulation Methods 0.000 claims abstract description 26
- 230000004044 response Effects 0.000 claims abstract description 24
- 238000013016 damping Methods 0.000 claims description 25
- 238000004364 calculation method Methods 0.000 claims description 15
- 230000008878 coupling Effects 0.000 claims description 14
- 238000010168 coupling process Methods 0.000 claims description 14
- 238000005859 coupling reaction Methods 0.000 claims description 14
- 239000007788 liquid Substances 0.000 claims description 13
- 238000005094 computer simulation Methods 0.000 claims description 11
- 230000000694 effects Effects 0.000 claims description 7
- 230000002159 abnormal effect Effects 0.000 claims description 6
- 230000004907 flux Effects 0.000 claims description 6
- 238000006073 displacement reaction Methods 0.000 claims description 3
- 238000001228 spectrum Methods 0.000 claims description 3
- 230000008569 process Effects 0.000 claims description 2
- 238000013461 design Methods 0.000 abstract description 6
- 238000004519 manufacturing process Methods 0.000 abstract description 6
- 239000002826 coolant Substances 0.000 abstract description 3
- 238000012821 model calculation Methods 0.000 abstract 1
- 230000009471 action Effects 0.000 description 14
- 230000004323 axial length Effects 0.000 description 5
- 230000001808 coupling effect Effects 0.000 description 4
- 238000011112 process operation Methods 0.000 description 4
- 230000000875 corresponding effect Effects 0.000 description 2
- 238000011161 development Methods 0.000 description 2
- 230000018109 developmental process Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 238000011156 evaluation Methods 0.000 description 2
- 239000011159 matrix material Substances 0.000 description 2
- 238000012360 testing method Methods 0.000 description 2
- 230000001052 transient effect Effects 0.000 description 2
- 230000006399 behavior Effects 0.000 description 1
- 230000002457 bidirectional effect Effects 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 238000012937 correction Methods 0.000 description 1
- 230000002596 correlated effect Effects 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000001050 lubricating effect Effects 0.000 description 1
- 238000011160 research Methods 0.000 description 1
- 230000035939 shock Effects 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 230000003068 static effect Effects 0.000 description 1
- 239000002918 waste heat Substances 0.000 description 1
Images
Landscapes
- Structures Of Non-Positive Displacement Pumps (AREA)
Abstract
基于梁有限元模型构建屏蔽式核主泵数字样机方法，属于核反应堆冷却剂泵设计和制造。构建步骤：一、依据核主泵零部件几何及装配关系，生成核主泵几何建模模块；二、在核主泵几何模型基础上，生成转子组件梁有限元建模模块、轴承支撑系统建模模块，及泵壳组件梁有限元建模模块；三、集成转子组件、轴承支撑系统及泵壳组件模型，建立梁有限元总体模型，生成核主泵总体建模模块，以核主泵运行参数下运行载荷数据库模块为信息支撑，构建核主泵三维数字样机；四、核主泵性能分析模块接收三维数字样机，调用梁有限元总体模型计算数据作为输入，输出核主泵动力学响应和噪声分析、抗震分析、零部件受力分析的仿真结果。优点：核主泵动力学特性分析准确。
A method for constructing a digital prototype of a shielded nuclear main pump based on a beam finite element model belongs to the design and manufacture of a nuclear reactor coolant pump. Construction steps: 1. Generate the geometric modeling module of the nuclear main pump according to the geometry and assembly relationship of the nuclear main pump; model module, and the beam finite element modeling module of the pump casing assembly; 3. Integrate the rotor assembly, bearing support system and pump casing assembly model, establish the beam finite element overall model, generate the nuclear main pump overall modeling module, and run the nuclear main pump The operating load database module under the parameters is the information support to build a three-dimensional digital prototype of the nuclear main pump; Fourth, the nuclear main pump performance analysis module receives the three-dimensional digital prototype, calls the beam finite element overall model calculation data as input, and outputs the nuclear main pump dynamic response and Simulation results of noise analysis, seismic analysis, and component force analysis. Advantages: The analysis of the dynamic characteristics of the nuclear main pump is accurate.
Description
Technical Field
The invention relates to a method for constructing a shielded nuclear main pump digital prototype based on a beam finite element model, belonging to the field of design and manufacture of a nuclear reactor coolant pump.
Technical Field
The nuclear main pump is a device for driving high-temperature, high-pressure and high-radioactivity working media in the nuclear island to circulate, transferring the heat energy of nuclear fission of the reactor core to the steam generator to generate steam and push the steam turbine to generate power, and is also the only device for continuous high-speed rotation in the nuclear island. The nuclear main pump is used as a component of a pressure-bearing boundary of a primary circuit, and is required to operate efficiently and stably under various complex working conditions, unplanned shutdown is avoided, and working media are strictly free of external leakage. Under transient catastrophe extreme working conditions such as earthquake, fire and the like, the operation is maintained by means of self inertia, and working media with enough flow are provided to take away the waste heat of the reactor core. Therefore, the design and manufacture of the nuclear main pump must master the operation dynamic response, the noise characteristic, the anti-seismic characteristic, the stress condition of parts, the stress distribution, the fatigue life and other conditions of the nuclear main pump.
The shielded nuclear main pump consists of two parts, namely a hydraulic mechanical part, a pump part, a driving part and a motor, and comprises main parts, such as a pump shell, a pump shaft, an impeller, a flywheel, a guide bearing, a stator and a rotor, a shielding sleeve, a thrust bearing and the like. The impeller of the pump and the rotor of the motor are fixed on the pump shaft and contained in a pressure-bearing boundary communicated with the main loop, so that zero leakage of coolant in the loop is ensured. The pump shell assembly is formed by assembling parts such as the pump shell, the guide vane, the motor stator, the shielding sleeve and the like. The pump shaft, the impeller, the flywheel, the motor rotor, the shielding sleeve and other parts are assembled to form the rotor assembly. The rotor assembly deadweight and the axial load generated by the hydraulic load of the impeller during operation are supported by the bidirectional thrust bearing, and the radial load is supported by the guide bearing. The thrust bearing comprises a plurality of thrust pads, and an upper balance block, a lower balance block and a supporting plate are arranged below the thrust pads. When the thrust pads deflect unevenly, the distributed load on each pad is automatically adjusted through the balance block, so that each pad can still form relatively uniform liquid film pressure under the transient deflection working condition of the rotor to a certain degree. At present, the modeling analysis of dynamic response, noise characteristics, anti-seismic characteristics and the like of a shielding type nuclear main pump mainly considers radial constraints of a guide bearing and clearance circulation in a rotor-bearing system, and neglects the coupling effect of a thrust bearing on transverse and longitudinal vibration, so that the evaluation of the vibration of a thrust bearing support system and the overall vibration of the nuclear main pump is difficult. In addition, the existing nuclear main pump dynamic characteristic analysis model only considers the action of one or two operation loads, and fails to show the coupling action of various loads including bearing lubricating liquid film force, clearance circulation force, centrifugal force, electromagnetic pulling force, hydrodynamic force, friction force under abnormal working conditions and the like.
The article "A full structural mechanical description of beam elements for motors in electrical machines" was reported by Poganski et al in 2015, and the finite element consistency description was performed on a Timoshenko beam of a motor rotor by changing a shape function. The method comprises the steps of analyzing structural behaviors of a motor rotor by using a developed finite element program, calculating static torsional load of the rotor and torsional deformation of a system torsional mode, considering a rotary damping system with spin softening and gyroscopic effects, analyzing critical rotating speed of the rotor according to eigen frequency calculated by rotating speed, and obviously influencing the warping of the cross section of a beam unit, so that the warping expansion finite element analysis precision is higher than that of a traditional finite element analysis method. A 'Dynamic effect of annular flow with fine axial length on the rotor' paper is reported by Cheng et al in 2016, a test bed for researching the influence of the clearance annular flow on the Dynamic characteristics of the rotor is established aiming at the Dynamic force effect of the limited axial length annular flow of the shielded nuclear main pump, an additional mass, damping and rigidity matrix of the clearance annular flow on the rotor is obtained through two-dimensional annular flow model analysis based on the bulk flow theory, the three-dimensional effect of the short-axis clearance annular flow is researched through the proposed additional mass, damping and rigidity matrix correction coefficients, when the axial length of the annular flow effect is changed, the change of the model frequency of the test bed predicted by a Dynamic fluid-solid coupling model is matched with the experimental result, and the Dynamic force of the short axial length is positively correlated with the square of the axial length.
The construction of a digital prototype capable of realizing the comprehensive evaluation of the dynamic response, the noise characteristic, the anti-seismic characteristic and other performances of the nuclear main pump has important engineering significance. Although the research on the numerical simulation of the dynamic characteristics of a hydraulic mechanical part, a pump and a driving part, and a motor of a nuclear main pump is carried out, the numerical simulation of a finite element model of the nuclear main pump has the characteristics of multivariable, strong coupling and nonlinearity, so that the current numerical simulation adopts a simplified modeling and solving process, or only one or two operation load modeling are carried out aiming at a local structure, a mature dynamic characteristic analysis method for comprehensively considering the characteristics of a shielding pump structure and multiple loads does not exist, and the working characteristics and the performance of the nuclear main pump under the conditions of high temperature, high pressure and high radioactivity are difficult to accurately reflect. Therefore, the method for developing the finite element method of the multi-load beam can accurately evaluate the problems of dynamic response, noise characteristics, anti-seismic characteristics, stress analysis of parts and the like of the nuclear main pump under the multi-load coupling effect, can provide a foundation for the design and manufacture of the nuclear main pump, and effectively reduces the development and operation cost of the nuclear main pump.
Disclosure of Invention
Objects and tasks of the invention: the problem that the existing nuclear main pump performance simulation numerical model only considers the action of one or two operation loads, fails to comprehensively consider the dynamic characteristics of multi-load and shield pump rotor coupling vibration and the like, and cannot accurately evaluate the characteristics of the nuclear main pump such as dynamic response, noise, shock resistance, stress analysis and the like is solved. The combined action of the seismic load, the impeller hydraulic load, the flywheel centrifugal force, the torque load, the friction load, the electromagnetic tension, the bearing liquid film rigidity and damping, the gap circulation additional mass, the rigidity, the damping and other operation loads under the full working condition of the shielded nuclear main pump is considered, and a shielded nuclear main pump digital prototype is constructed.
The technical scheme adopted by the invention is as follows: the method for constructing the shielded nuclear main pump digital prototype based on the beam finite element model comprises a nuclear main pump geometric modeling module, a rotor assembly beam finite element modeling module, a bearing support system modeling module, a pump shell assembly beam finite element modeling module, a nuclear main pump overall modeling module, a nuclear main pump running load database module and a nuclear main pump performance analysis module, and is constructed according to the following steps:
(1) establishing a geometric model for finite element modeling of a nuclear main pump beam according to geometric structures and assembly relations of a pump shell, a pump shaft, an impeller, a flywheel, a guide bearing, a motor stator and rotor, a shield sleeve and a thrust bearing of the nuclear main pump;
(2) on the basis of a geometric model of a nuclear main pump, aiming at a rotor assembly formed by an impeller, a flywheel, a pump shaft, a motor rotor and a shielding sleeve, simulating the transverse vibration of the rotor assembly by using a Timoshenko beam model, and simulating the axial vibration of the rotor assembly by using a pull rod model to generate a rotor assembly beam finite element modeling module;
(3) on the basis of a geometric model of a nuclear main pump, aiming at a bearing support system consisting of a thrust disc of a thrust bearing, a thrust shoe, an upper balance block, a lower balance block and a support plate, a mass block model of the upper balance block and the lower balance block simulates rotation and axial vibration of the bearing support system, and a mass block model of the thrust shoe and the support plate simulates axial vibration of the bearing support system to generate a bearing support system modeling module;
(4) on the basis of a geometric model of a nuclear main pump, aiming at a pump shell assembly formed by a pump shell, a guide vane, a motor stator and a shielding sleeve, a Timoshenko beam model is used for simulating transverse vibration of the pump shell assembly, a pull rod model is used for simulating axial vibration of the pump shell assembly, and a pump shell assembly beam finite element modeling module is generated;
(5) integrating a rotor assembly beam finite element model, a bearing support system model and a pump shell assembly beam finite element model, and establishing a nuclear main pump beam finite element overall model;
(6) taking the operating parameters of the nuclear main pump as input, and generating a nuclear main pump operating load database module by considering the seismic load, the impeller hydraulic load, the flywheel centrifugal force, the torque load, the friction load, the electromagnetic tension, the bearing liquid film rigidity and damping, and the gap circulation additional mass, rigidity and damping under all working conditions;
(7) under the operation parameters of the nuclear main pump, using an operation load database module as information support of a finite element overall model of the nuclear main pump beam to generate a nuclear main pump overall modeling module and construct a nuclear main pump three-dimensional digital prototype;
(8) the nuclear main pump three-dimensional digital prototype is received through a nuclear main pump performance analysis module, and according to analysis requests of nuclear main pump dynamic response and noise analysis, anti-seismic characteristic analysis and part stress analysis, beam finite element overall model coupling calculation data is called as input, and a nuclear main pump dynamic performance simulation result is output or output after physical process operation.
The nuclear main pump general modeling module considers an impeller hydraulic load, a flywheel centrifugal force, a motor rotor and shielding sleeve torque load and an electromagnetic tension which are related to a rotor assembly beam finite element model, a friction load between parts under abnormal working conditions, flywheel and shielding sleeve gap circulation additional mass, rigidity and damping action in a beam finite element general model, thrust bearing liquid film rigidity and damping action which are related to a bearing support system model, an earthquake load, a motor stator and shielding sleeve electromagnetic tension which are related to a pump housing assembly beam finite element model, calls the running load of the nuclear main pump running load database module, and constructs a shielding type nuclear main pump three-dimensional digital prototype.
The nuclear main pump performance analysis module calls corresponding loads in a nuclear main pump running load database as input according to analysis requests of nuclear main pump dynamic response and noise, outputs natural frequency and vibration type of the whole structure of the nuclear main pump, rotor axis track and critical rotating speed, pump shell vibration and a time-course response simulation result of a thrust bearing support system, outputs the natural frequency and vibration type of the coupling of the nuclear main pump and a main pipeline, and outputs a vibration noise simulation result of the nuclear main pump and the main pipeline, based on the structural vibration response of the nuclear main pump, outputs the vibration noise simulation result of the nuclear main pump after calculation, and based on radial magnetic flux density and tangential magnetic flux density of the nuclear main pump gap annulus, outputs an electromagnetic noise simulation result after calculation.
And the nuclear main pump performance analysis module calls a seismic load spectrum in a nuclear main pump operation load database as input according to the analysis request of the seismic characteristics of the nuclear main pump, and outputs a nuclear main pump dynamic characteristic simulation result under the seismic condition.
The nuclear main pump performance analysis module calls deformation and displacement of the nuclear main pump parts as input according to analysis requests of stress of the nuclear main pump parts, and outputs internal force of the nuclear main pump parts and contact force between the nuclear main pump parts. And (3) calling the internal force of the parts and the contact force between the parts according to the calculation data of the stress analysis of the parts of the nuclear main pump, and outputting the fatigue life analysis result of the parts.
The invention has the advantages that: compared with the traditional modeling method, the method for constructing the shielded nuclear main pump digital prototype comprehensively considers the dynamic characteristics of the multi-load and the coupling vibration of the rotor of the nuclear main pump, meets the performance simulation requirements of the nuclear main pump with the characteristics of multivariable, strong coupling and nonlinearity, accurately evaluates the dynamic characteristics and performances of the nuclear main pump under the multi-load coupling action, such as dynamic response, noise characteristics, anti-seismic characteristics, stress analysis of parts and the like, can provide a basis for the design and manufacture of the nuclear main pump, and reduces the development and running cost of the nuclear main pump.
Drawings
FIG. 1 is a work flow diagram of a method for constructing a shielded nuclear main pump digital prototype based on a beam finite element model.
FIG. 2 is a schematic diagram of load effects associated with components in the overall modeling module of the nuclear main pump.
Detailed Description
The details of the present invention are further illustrated below with reference to specific examples:
the method for constructing the shielding type nuclear main pump digital prototype realizes the modeling and coupling analysis of the beam finite element model by utilizing the shielding type nuclear main pump geometric modeling module, the rotor assembly beam finite element modeling module, the bearing support system modeling module, the pump shell assembly beam finite element modeling module, the nuclear main pump overall modeling module, the nuclear main pump running load database module and the nuclear main pump performance analysis module, and provides the method for constructing the shielding type nuclear main pump digital prototype, which can accurately represent the working characteristics and performance of the nuclear main pump and reduce the design, manufacturing and running costs of the nuclear main pump.
Embodiment 1 will be described with reference to the drawings of the present invention, wherein the technical solutions of the present invention applied to the analysis of the dynamic response and noise characteristics of the nuclear main pump are described.
As shown in fig. 1, the method for constructing a shielded nuclear main pump digital prototype based on a beam finite element model, provided by the invention, is used for constructing a nuclear main pump three-dimensional digital prototype, and comprises a nuclear main pump geometric modeling module, a rotor assembly beam finite element modeling module, a bearing support system modeling module, a pump shell assembly beam finite element modeling module, a nuclear main pump overall modeling module, a nuclear main pump operation load database module and a nuclear main pump performance analysis module, wherein the method is constructed according to the following steps in consideration of the nuclear main pump dynamic response and noise characteristic analysis requirements:
(1) establishing a geometric model for finite element modeling of a nuclear main pump beam according to geometric structures and assembly relations of a pump shell, a pump shaft, an impeller, a flywheel, a guide bearing, a motor stator and rotor, a shield sleeve and a thrust bearing of the nuclear main pump;
(2) on the basis of a geometric model of a nuclear main pump, aiming at a rotor assembly formed by an impeller, a flywheel, a pump shaft, a motor rotor and a shielding sleeve, simulating the transverse vibration of the rotor assembly by using a Timoshenko beam model, and simulating the axial vibration of the rotor assembly by using a pull rod model to generate a rotor assembly beam finite element modeling module;
(3) on the basis of a geometric model of a nuclear main pump, aiming at a bearing support system consisting of a thrust disc of a thrust bearing, a thrust shoe, an upper balance block, a lower balance block and a support plate, a mass block model of the upper balance block and the lower balance block simulates rotation and axial vibration of the bearing support system, and a mass block model of the thrust shoe and the support plate simulates axial vibration of the bearing support system to generate a bearing support system modeling module;
(4) on the basis of a geometric model of a nuclear main pump, aiming at a pump shell assembly formed by a pump shell, a guide vane, a motor stator and a shielding sleeve, a Timoshenko beam model is used for simulating transverse vibration of the pump shell assembly, a pull rod model is used for simulating axial vibration of the pump shell assembly, and a pump shell assembly beam finite element modeling module is generated;
(5) integrating a rotor assembly beam finite element model, a bearing support system model and a pump shell assembly beam finite element model, and establishing a nuclear main pump beam finite element overall model;
(6) taking the operating parameters of the nuclear main pump as input, and generating a nuclear main pump operating load database module by considering the seismic load, the impeller hydraulic load, the flywheel centrifugal force, the torque load, the friction load, the electromagnetic tension, the bearing liquid film rigidity and damping, and the gap circulation additional mass, rigidity and damping under all working conditions;
(7) under the operation parameters of the nuclear main pump, using an operation load database module as information support of a finite element overall model of the nuclear main pump beam to generate a nuclear main pump overall modeling module and construct a nuclear main pump three-dimensional digital prototype;
(8) the nuclear main pump three-dimensional digital prototype is received through a nuclear main pump performance analysis module, and according to analysis requests of nuclear main pump dynamic response and noise analysis, anti-seismic characteristic analysis and part stress analysis, beam finite element overall model coupling calculation data is called as input, and a nuclear main pump dynamic performance simulation result is output or output after physical process operation.
As shown in fig. 2, the load action associated with the parts considered in the nuclear main pump beam finite element overall model by the nuclear main pump overall modeling module includes the impeller hydraulic load, the flywheel centrifugal force, the motor rotor and shielding sleeve torque load and electromagnetic tension associated with the rotor assembly beam finite element model, the friction load between the parts under abnormal conditions, the additional mass, the rigidity and the damping action of the gap circulation between the flywheel and the shielding sleeve, the thrust bearing liquid film rigidity and the damping action associated with the bearing support system model, the earthquake load, the motor stator and the shielding sleeve electromagnetic tension associated with the pump housing assembly beam finite element model, the operation load of the nuclear main pump operation load database module is called, and the shielded nuclear main pump three-dimensional digital prototype is constructed.
The nuclear main pump performance analysis module calls corresponding loads in a nuclear main pump running load database as input according to analysis requests of nuclear main pump dynamic response and noise, outputs natural frequency and vibration type of the whole structure of the nuclear main pump, rotor axis track and critical rotating speed, pump shell vibration and a time-course response simulation result of a thrust bearing support system, outputs the natural frequency and vibration type of the coupling of the nuclear main pump and a main pipeline, and outputs a vibration noise simulation result of the nuclear main pump and the main pipeline, based on the structural vibration response of the nuclear main pump, outputs the vibration noise simulation result of the nuclear main pump after calculation, and based on radial magnetic flux density and tangential magnetic flux density of the nuclear main pump gap annulus, outputs an electromagnetic noise simulation result after calculation.
Embodiment 2 will be described with reference to the drawings of the present invention, wherein a technical scheme of an embodiment of the present invention applied to the seismic characteristic analysis of a nuclear main pump is described.
As shown in fig. 1, the method for constructing a shielded nuclear main pump digital prototype based on a beam finite element model, provided by the invention, is used for constructing a nuclear main pump three-dimensional digital prototype, and comprises a nuclear main pump geometric modeling module, a rotor assembly beam finite element modeling module, a bearing support system modeling module, a pump shell assembly beam finite element modeling module, a nuclear main pump overall modeling module, a nuclear main pump running load database module and a nuclear main pump performance analysis module, wherein the method is constructed according to the following steps in consideration of the nuclear main pump seismic characteristic analysis requirements:
(1) establishing a geometric model for finite element modeling of a nuclear main pump beam according to geometric structures and assembly relations of a pump shell, a pump shaft, an impeller, a flywheel, a guide bearing, a motor stator and rotor, a shield sleeve and a thrust bearing of the nuclear main pump;
(2) on the basis of a geometric model of a nuclear main pump, aiming at a rotor assembly formed by an impeller, a flywheel, a pump shaft, a motor rotor and a shielding sleeve, simulating the transverse vibration of the rotor assembly by using a Timoshenko beam model, and simulating the axial vibration of the rotor assembly by using a pull rod model to generate a rotor assembly beam finite element modeling module;
(3) on the basis of a geometric model of a nuclear main pump, aiming at a bearing support system consisting of a thrust disc of a thrust bearing, a thrust shoe, an upper balance block, a lower balance block and a support plate, a mass block model of the upper balance block and the lower balance block simulates rotation and axial vibration of the bearing support system, and a mass block model of the thrust shoe and the support plate simulates axial vibration of the bearing support system to generate a bearing support system modeling module;
(4) on the basis of a geometric model of a nuclear main pump, aiming at a pump shell assembly formed by a pump shell, a guide vane, a motor stator and a shielding sleeve, a Timoshenko beam model is used for simulating transverse vibration of the pump shell assembly, a pull rod model is used for simulating axial vibration of the pump shell assembly, and a pump shell assembly beam finite element modeling module is generated;
(5) integrating a rotor assembly beam finite element model, a bearing support system model and a pump shell assembly beam finite element model, and establishing a nuclear main pump beam finite element overall model;
(6) taking the operating parameters of the nuclear main pump as input, and generating a nuclear main pump operating load database module by considering the seismic load, the impeller hydraulic load, the flywheel centrifugal force, the torque load, the friction load, the electromagnetic tension, the bearing liquid film rigidity and damping, and the gap circulation additional mass, rigidity and damping under all working conditions;
(7) under the operation parameters of the nuclear main pump, using an operation load database module as information support of a finite element overall model of the nuclear main pump beam to generate a nuclear main pump overall modeling module and construct a nuclear main pump three-dimensional digital prototype;
(8) the nuclear main pump three-dimensional digital prototype is received through a nuclear main pump performance analysis module, and according to analysis requests of nuclear main pump dynamic response and noise analysis, anti-seismic characteristic analysis and part stress analysis, beam finite element overall model coupling calculation data is called as input, and a nuclear main pump dynamic performance simulation result is output or output after physical process operation.
As shown in fig. 2, the load action associated with the parts considered in the nuclear main pump beam finite element overall model by the nuclear main pump overall modeling module includes the impeller hydraulic load, the flywheel centrifugal force, the motor rotor and shielding sleeve torque load and electromagnetic tension associated with the rotor assembly beam finite element model, the friction load between the parts under abnormal conditions, the additional mass, the rigidity and the damping action of the gap circulation between the flywheel and the shielding sleeve, the thrust bearing liquid film rigidity and the damping action associated with the bearing support system model, the earthquake load, the motor stator and the shielding sleeve electromagnetic tension associated with the pump housing assembly beam finite element model, the operation load of the nuclear main pump operation load database module is called, and the shielded nuclear main pump three-dimensional digital prototype is constructed.
And the nuclear main pump performance analysis module calls a seismic load spectrum in a nuclear main pump operation load database as input according to the analysis request of the seismic characteristics of the nuclear main pump, and outputs a nuclear main pump dynamic characteristic simulation result under the seismic condition.
Embodiment 3 will describe an embodiment technical solution of the invention applied to stress analysis of parts of a nuclear main pump, with reference to the drawings of the invention.
As shown in fig. 1, the method for constructing a shielded nuclear main pump digital prototype based on a beam finite element model, provided by the invention, is used for constructing a nuclear main pump three-dimensional digital prototype, and comprises a nuclear main pump geometric modeling module, a rotor assembly beam finite element modeling module, a bearing support system modeling module, a pump shell assembly beam finite element modeling module, a nuclear main pump overall modeling module, a nuclear main pump running load database module and a nuclear main pump performance analysis module, wherein the method is constructed according to the following steps in consideration of stress analysis requirements of parts of the nuclear main pump:
(1) establishing a geometric model for finite element modeling of a nuclear main pump beam according to geometric structures and assembly relations of a pump shell, a pump shaft, an impeller, a flywheel, a guide bearing, a motor stator and rotor, a shield sleeve and a thrust bearing of the nuclear main pump;
(2) on the basis of a geometric model of a nuclear main pump, aiming at a rotor assembly formed by an impeller, a flywheel, a pump shaft, a motor rotor and a shielding sleeve, simulating the transverse vibration of the rotor assembly by using a Timoshenko beam model, and simulating the axial vibration of the rotor assembly by using a pull rod model to generate a rotor assembly beam finite element modeling module;
(3) on the basis of a geometric model of a nuclear main pump, aiming at a bearing support system consisting of a thrust disc of a thrust bearing, a thrust shoe, an upper balance block, a lower balance block and a support plate, a mass block model of the upper balance block and the lower balance block simulates rotation and axial vibration of the bearing support system, and a mass block model of the thrust shoe and the support plate simulates axial vibration of the bearing support system to generate a bearing support system modeling module;
(4) on the basis of a geometric model of a nuclear main pump, aiming at a pump shell assembly formed by a pump shell, a guide vane, a motor stator and a shielding sleeve, a Timoshenko beam model is used for simulating transverse vibration of the pump shell assembly, a pull rod model is used for simulating axial vibration of the pump shell assembly, and a pump shell assembly beam finite element modeling module is generated;
(5) integrating a rotor assembly beam finite element model, a bearing support system model and a pump shell assembly beam finite element model, and establishing a nuclear main pump beam finite element overall model;
(6) taking the operating parameters of the nuclear main pump as input, and generating a nuclear main pump operating load database module by considering the seismic load, the impeller hydraulic load, the flywheel centrifugal force, the torque load, the friction load, the electromagnetic tension, the bearing liquid film rigidity and damping, and the gap circulation additional mass, rigidity and damping under all working conditions;
(7) under the operation parameters of the nuclear main pump, using an operation load database module as information support of a finite element overall model of the nuclear main pump beam to generate a nuclear main pump overall modeling module and construct a nuclear main pump three-dimensional digital prototype;
(8) the nuclear main pump three-dimensional digital prototype is received through a nuclear main pump performance analysis module, and according to analysis requests of nuclear main pump dynamic response and noise analysis, anti-seismic characteristic analysis and part stress analysis, beam finite element overall model coupling calculation data is called as input, and a nuclear main pump dynamic performance simulation result is output or output after physical process operation.
As shown in fig. 2, the load action associated with the parts considered in the nuclear main pump beam finite element overall model by the nuclear main pump overall modeling module includes the impeller hydraulic load, the flywheel centrifugal force, the motor rotor and shielding sleeve torque load and electromagnetic tension associated with the rotor assembly beam finite element model, the friction load between the parts under abnormal conditions, the additional mass, the rigidity and the damping action of the gap circulation between the flywheel and the shielding sleeve, the thrust bearing liquid film rigidity and the damping action associated with the bearing support system model, the earthquake load, the motor stator and the shielding sleeve electromagnetic tension associated with the pump housing assembly beam finite element model, the operation load of the nuclear main pump operation load database module is called, and the shielded nuclear main pump three-dimensional digital prototype is constructed.
The nuclear main pump performance analysis module calls deformation and displacement of the nuclear main pump parts as input according to analysis requests of stress of the nuclear main pump parts, and outputs internal force of the nuclear main pump parts and contact force between the nuclear main pump parts. And (3) calling the internal force of the parts and the contact force between the parts according to the calculation data of the stress analysis of the parts of the nuclear main pump, and outputting the fatigue life analysis result of the parts.
Claims (6)
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910854567.8A CN110598316B (en) | 2019-09-10 | 2019-09-10 | Construction of digital prototype method of shielded nuclear main pump based on beam finite element model |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201910854567.8A CN110598316B (en) | 2019-09-10 | 2019-09-10 | Construction of digital prototype method of shielded nuclear main pump based on beam finite element model |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN110598316A CN110598316A (en) | 2019-12-20 |
| CN110598316B true CN110598316B (en) | 2021-07-27 |
Family
ID=68858725
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201910854567.8A Active CN110598316B (en) | 2019-09-10 | 2019-09-10 | Construction of digital prototype method of shielded nuclear main pump based on beam finite element model |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN110598316B (en) |
Families Citing this family (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111209639B (en) * | 2020-02-17 | 2024-05-03 | 合肥工业大学 | Efficient quantitative modeling method for impeller-bearing-rotor system |
| CN111967075B (en) * | 2020-07-10 | 2024-02-02 | 中国核电工程有限公司 | Structural analysis method and device for pressure-bearing anti-seismic rectangular air pipe |
| CN113536649B (en) * | 2021-09-09 | 2021-11-19 | 东方法马通核泵有限责任公司 | Simplified model construction method and beam unit model construction method of nuclear power main pump structure |
| CN114169199B (en) * | 2021-12-03 | 2023-03-24 | 东方电气集团东方电机有限公司 | Method for analyzing electromagnetic and structural coupling dynamics of stator winding end |
| CN116384009B (en) * | 2023-05-31 | 2023-08-11 | 安徽新沪屏蔽泵有限责任公司 | Simulation prediction method, device and equipment for energy efficiency level of canned motor pump |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102184285A (en) * | 2011-05-03 | 2011-09-14 | 三一集团有限公司 | Digital prototyping design integrated development method and system |
| CN106015082A (en) * | 2016-05-13 | 2016-10-12 | 江苏大学 | Impeller optimized design method capable of prolonging running down time of reactor coolant pump |
| CN108005948A (en) * | 2017-11-06 | 2018-05-08 | 大连理工大学 | Hydraulic model and water passage for large pressurized water reactor power station core main pump |
| CN108073736A (en) * | 2016-11-14 | 2018-05-25 | 沈阳鼓风机集团核电泵业有限公司 | Core main pump heat-proof device simplifies Equivalent analysis method |
| CN108256279A (en) * | 2018-03-20 | 2018-07-06 | 大连理工大学 | One seed nucleus main pump polymer matrix composites tilting bush water lubricating thrust bearing optimum design method |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US9158303B2 (en) * | 2012-03-27 | 2015-10-13 | General Electric Company | Systems and methods for improved reliability operations |
-
2019
- 2019-09-10 CN CN201910854567.8A patent/CN110598316B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN102184285A (en) * | 2011-05-03 | 2011-09-14 | 三一集团有限公司 | Digital prototyping design integrated development method and system |
| CN106015082A (en) * | 2016-05-13 | 2016-10-12 | 江苏大学 | Impeller optimized design method capable of prolonging running down time of reactor coolant pump |
| CN108073736A (en) * | 2016-11-14 | 2018-05-25 | 沈阳鼓风机集团核电泵业有限公司 | Core main pump heat-proof device simplifies Equivalent analysis method |
| CN108005948A (en) * | 2017-11-06 | 2018-05-08 | 大连理工大学 | Hydraulic model and water passage for large pressurized water reactor power station core main pump |
| CN108256279A (en) * | 2018-03-20 | 2018-07-06 | 大连理工大学 | One seed nucleus main pump polymer matrix composites tilting bush water lubricating thrust bearing optimum design method |
Non-Patent Citations (2)
| Title |
|---|
| 核主泵制造的基础理论问题研究进展;雷明凯;《核电研发》;20180331;第11卷(第1期);第51-58页 * |
| 核主泵压力脉动及其诱导振动研究进展;雷明凯 等;《中国核电》;20190630;第12卷(第3期);第275-279页 * |
Also Published As
| Publication number | Publication date |
|---|---|
| CN110598316A (en) | 2019-12-20 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN110598316B (en) | Construction of digital prototype method of shielded nuclear main pump based on beam finite element model | |
| CN110598317B (en) | Multiphysics coupling method to build digital prototype of shielded nuclear main pump | |
| Kiciński et al. | Steam microturbines in distributed cogeneration | |
| CN103366050B (en) | A kind of high-speed electric main shaft power-thermal coupling modeling method | |
| Wang et al. | Nonlinear dynamic response and stability of a rod fastening rotor with internal damping effect | |
| Ashtekar et al. | Experimental and analytical investigation of high speed turbocharger ball bearings | |
| CN109033488A (en) | A kind of pump-storage generator durability analysis method based on water electromechanical Coupling Model | |
| Xu et al. | Computational model for investigating the influence of unbalanced magnetic pull on the radial vibration of large hydro-turbine generators | |
| Li et al. | Labyrinth seal rotordynamic characteristics part I: Operational conditions effects | |
| Xie et al. | Rotor dynamic analysis of the vertical hydro-hybrid bearing rotor coupled system of a two-circuit main loop liquid sodium pump system | |
| Zhou et al. | A novel axial vibration model of multistage pump rotor system with dynamic force of balance disc | |
| Baxi et al. | Rotor scale model tests for power conversion unit of GT-MHR | |
| Kim et al. | Mesoscale foil gas bearings for palm-sized turbomachinery: design, manufacturing, and modeling | |
| Jiang et al. | Fluid-structure interaction analysis of annular seals and rotor systems in multi-stage pumps | |
| Han et al. | Coupling Vibration Analysis of Turbine Shared Support Rotor‐Bearing System with Squeeze Film Dampers | |
| Liu et al. | Optimal vibration reduction of flexible rotor systems by the virtual bearing method | |
| Brito Jr et al. | Model-based vibration condition monitoring for fault detection and diagnostics in large hydrogenerators | |
| Sikanen | Dynamic analysis of rotating systems including contact and thermal-induced effects | |
| Pilotto et al. | Vibration control of a gas turbine-generator rotor in a combined cycle system by means of active magnetic bearings | |
| Shen et al. | Study on the cantilever ratio optimization of high-temperature molten salt pump for molten salt reactor based on structural integrity | |
| Xu et al. | Research on vibration characteristics and reasons of thermal power generating units | |
| Song et al. | Impact of Installation Deviations on the Dynamic Characteristics of the Shaft System for 1 Gigawatt Hydro-Generator Unit. | |
| Abbood et al. | Numerical investigation on the vibration reduction of rotating shaft using different groove shapes of tilt bearing | |
| Lobitz et al. | Comparison of finite-element predictions and experimental data for the forced response of the DOE 100-kW vertical-axis wind turbine | |
| Nässelqvist et al. | Resonance problems in vertical hydropower unit after turbine upgrade |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |