CN112613148A - Nuclear power equipment design method based on numerical analysis deformation data - Google Patents

Nuclear power equipment design method based on numerical analysis deformation data Download PDF

Info

Publication number
CN112613148A
CN112613148A CN202011615181.0A CN202011615181A CN112613148A CN 112613148 A CN112613148 A CN 112613148A CN 202011615181 A CN202011615181 A CN 202011615181A CN 112613148 A CN112613148 A CN 112613148A
Authority
CN
China
Prior art keywords
precision
characteristic
model
nuclear power
power equipment
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.)
Pending
Application number
CN202011615181.0A
Other languages
Chinese (zh)
Inventor
孙永平
李蕤
王铮
朱永波
杨春辉
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China First Heavy Industries Co Ltd
CFHI Dalian Engineering and Technology Co Ltd
Original Assignee
China First Heavy Industries Co Ltd
CFHI Dalian Engineering and Technology Co Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by China First Heavy Industries Co Ltd, CFHI Dalian Engineering and Technology Co Ltd filed Critical China First Heavy Industries Co Ltd
Priority to CN202011615181.0A priority Critical patent/CN112613148A/en
Publication of CN112613148A publication Critical patent/CN112613148A/en
Pending legal-status Critical Current

Links

Images

Classifications

    • GPHYSICS
    • G06COMPUTING; CALCULATING OR COUNTING
    • G06FELECTRIC DIGITAL DATA PROCESSING
    • G06F30/00Computer-aided design [CAD]
    • G06F30/10Geometric CAD
    • G06F30/17Mechanical parametric or variational design
    • GPHYSICS
    • G06COMPUTING; CALCULATING OR COUNTING
    • G06FELECTRIC DIGITAL DATA PROCESSING
    • G06F30/00Computer-aided design [CAD]
    • G06F30/20Design optimisation, verification or simulation
    • G06F30/23Design optimisation, verification or simulation using finite element methods [FEM] or finite difference methods [FDM]
    • GPHYSICS
    • G06COMPUTING; CALCULATING OR COUNTING
    • G06FELECTRIC DIGITAL DATA PROCESSING
    • G06F2111/00Details relating to CAD techniques
    • G06F2111/10Numerical modelling

Abstract

The invention discloses a nuclear power equipment design method based on numerical analysis deformation data, which belongs to the technical field of nuclear power equipment. According to the invention, the precision characteristic analysis module program is added in the numerical calculation software, so that the deformation data of the installation surface in the process of research and development can be specified, and technical support is provided for precision design, thus the research and development efficiency and quality of nuclear power equipment are effectively improved, and the precision analysis problem in the process of designing the nuclear power equipment is solved.

Description

Nuclear power equipment design method based on numerical analysis deformation data
Technical Field
The invention relates to the technical field of nuclear power equipment, in particular to a nuclear power equipment design method based on numerical analysis deformation data.
Background
With the development of nuclear power energy industry, the research and development requirements of large-scale nuclear island main equipment are more and more increased, such as reactor pressure vessels of third-generation pressurized water reactors, fourth-generation sodium-cooled reactors, lead-bismuth reactors and molten salt reactors, refueling devices and the like. The nuclear island main equipment is mainly researched and designed by adopting an analysis design method, and the regulations of relevant standards such as ASME BPVC third volume, RCC and the like for evaluating the stress of the containers are mainly consulted abroad in the analysis design; the domestic numerical analysis process mainly follows the general rule of finite element mechanical analysis of the structure of the GB/T33582 and 2017 mechanical products, and the finite element analysis and calculation are carried out on the structure, but the post-processing program of the numerical calculation software has no analysis and evaluation method of the precision characteristic.
The precision problem needs to be considered in the design process of nuclear power equipment. For example, the nuclear island main equipment mainly comprises a nuclear reactor pressure vessel, refueling equipment and the like, and the structure is mainly shaped by a numerical calculation method in the research and development design stage. The current general numerical calculation processing software, such as ANSYS, MARC, ABAQUS and the like, mainly comprises the following analysis processes: physical modeling → finite element discrete modeling (pre-processing) → formation and solution of finite element equations → interpretation and display of results (post-processing). Wherein, the post-processing program has the function of further processing and graphically displaying the calculation result which is indicated to be output by the user in the pre-processing program. The display mode of the displacement calculation result in the post-processing generally includes the following modes: contour line display, cloud picture display, vector display, path display, history display and the like. In the process of research and development and design of nuclear power container equipment, designers need to qualitatively evaluate the installation accuracy characteristics of container interfaces. For example, in the design process of a third generation reactor type Hualong I nuclear reactor pressure vessel, the flatness of the equipment installation surface of the reactor internals needs to be evaluated; for example, the precision of the installation surfaces of large bearings, refueling devices, steam generators and other equipment on the pressure vessels of the four-generation reactors, such as sodium-cooled fast reactors, molten salt reactors, lead bismuth reactors and the like, needs to be evaluated. The traditional post-processing program of the general numerical calculation processing software cannot analyze the geometric shape position error of the equipment installation surface.
Disclosure of Invention
The invention provides a nuclear power equipment design method based on numerical analysis deformation data, which is a convenient post-processing method of numerical calculation software, and can specify the deformation data of the installation surface in the development process and provide technical support for precision design, thereby effectively improving the efficiency and quality of nuclear power equipment research and development and solving the problem of precision analysis evaluation in the nuclear power equipment design process.
In order to solve the technical problems, the technical scheme adopted by the invention is as follows:
a nuclear power equipment design method based on numerical analysis deformation data comprises the following steps:
step 1: establishing a numerical model for nuclear power equipment and carrying out numerical calculation to obtain a numerical calculation result;
step 2: extracting an equipment installation surface with precision requirements according to design input of nuclear power equipment, and determining geometric characteristic elements of the equipment installation surface;
and step 3: defining a reference standard for precision evaluation;
and 4, step 4: extracting node deformation displacement information of geometric characteristic elements of the installation surface of the nuclear power equipment from the numerical calculation result;
and 5: determining the requirement of precision evaluation aiming at the precision characteristic requirement of the installation surface of the nuclear power equipment, and establishing a precision characteristic evaluation model;
step 6: performing data fitting on the deformation elements by adopting a least square method, and performing fitting element parameter identification at different moments;
and 7: calculating the precision characteristics of equipment installation surfaces at different moments according to the precision characteristic evaluation model;
and 8: judging whether the precision characteristic meets the requirement of a precision allowable value of the structural design, if the precision characteristic does not meet the requirement, returning to the step 1, modifying the numerical model and carrying out numerical calculation again;
and step 9: and if the precision characteristic meets the requirement, finishing the calculation, outputting a calculation result and forming a calculation report.
Preferably, the accuracy characteristic evaluation model includes: a shape accuracy model, a direction accuracy model, a position accuracy model, and a run-out accuracy model.
Preferably, the shape accuracy model comprises a straightness accuracy characteristic, a flatness accuracy characteristic, a roundness accuracy characteristic, a cylindricity accuracy characteristic, a line profile accuracy characteristic and a surface profile accuracy characteristic;
the direction precision model comprises a parallelism precision characteristic, a perpendicularity precision characteristic and an inclination precision characteristic;
the position precision model comprises a position precision characteristic, a concentricity precision characteristic, a coaxiality precision characteristic and a symmetry precision characteristic;
the run-out precision model comprises a circular run-out precision characteristic and a full run-out precision characteristic.
Preferably, step 1 comprises:
step A: extracting the precision geometric tolerance requirement of each equipment mounting surface according to the design input of the nuclear power equipment, and taking the precision geometric tolerance requirement as a permissible value of the structural design precision;
and B: inputting a drawing according to the design of nuclear power equipment, and establishing a geometric model;
and C: inputting material attributes of nuclear power equipment, applying mechanical, thermal load and constraint boundary conditions, and determining a calculation unit;
step D: establishing a finite element discrete model according to the geometric model, and dividing grids to form a numerical model;
step E: determining an analysis solving method aiming at the calculation purpose, and calculating the time step length under the conditions of meeting the convergence, the calculation precision and the computer resources;
step F: solving and calculating the numerical model to obtain deformation calculation results at different moments;
step G: and analyzing the grid quality and sensitivity to ensure the accuracy of grid division.
Preferably, in the step B, the geometric model is simplified, and the detailed characteristics of the geometric model according to the edges, the small bosses and the small grooves of the structure are considered on the premise of ensuring the finite element analysis precision of the concerned part.
Preferably, in step D, when the grid is divided, the stress slow change region is coarsened, and the stress rapid change region is refined.
Preferably, the analytical solution method comprises a static analysis method and a dynamic analysis method.
The invention has the advantages and positive effects that:
1. according to the invention, the precision characteristic analysis module program is added in the numerical calculation software, so that the deformation data of the installation surface in the process of research and development can be specified, and technical support is provided for precision design, thus the research and development efficiency and quality of nuclear power equipment are effectively improved, and the precision analysis problem in the process of designing the nuclear power equipment is solved.
2. The invention solves the problem that the traditional post-processing program of the general numerical calculation processing software cannot analyze the geometric shape position error of the equipment installation surface.
3. The method is a convenient post-processing method of numerical calculation software, the precision characteristic calculation analysis is used as the extension of the design stress analysis evaluation of the nuclear power equipment, and the method is simple and has strong operability.
Drawings
In order to more clearly illustrate the embodiments of the present invention or the technical solutions in the prior art, the drawings needed to be used in the description of the embodiments or the prior art will be briefly introduced below, and it is obvious that the drawings in the following description are some embodiments of the present invention, and for those skilled in the art, other drawings can be obtained according to these drawings without creative efforts.
FIG. 1 is a flow chart of a design method of nuclear power equipment in an embodiment of the invention;
FIG. 2 is a schematic diagram of the precision extraction position and precision analysis of the nuclear power equipment.
Detailed Description
The invention provides a nuclear power equipment design method based on numerical analysis deformation data, which is developed aiming at the problem that the geometric shape position error of an equipment installation surface cannot be analyzed in the traditional general numerical calculation processing software post-processing program.
In order to make the technical solutions of the present invention better understood, the technical solutions in the embodiments of the present invention will be clearly and completely described below with reference to the drawings in the embodiments of the present invention, and it is obvious that the described embodiments are only a part of the embodiments of the present invention, and not all of the embodiments. All other embodiments, which can be derived by a person skilled in the art from the embodiments given herein without making any creative effort, shall fall within the protection scope of the present invention.
As shown in fig. 1, an embodiment of the present invention provides a nuclear power equipment design method based on numerical analysis deformation data, where a nuclear power equipment design system includes a preprocessing and solving module and a precision characteristic post-processing analysis module, and the nuclear power equipment design method includes the following steps:
step 101: extracting the precision geometric tolerance requirement of each equipment mounting surface according to the design input of nuclear power equipment, and taking the precision geometric tolerance requirement as a permissible value of structural design precision;
step 102: inputting a drawing according to the design of nuclear power equipment, and establishing a geometric model;
during specific implementation, the geometric model is simplified, and the detail characteristics of the geometric model such as edges, small bosses, small grooves and the like according to the structure are considered as far as possible on the premise of ensuring the finite element analysis precision of the concerned part;
step 103: inputting material properties of nuclear power equipment, applying mechanical load, thermal load and the like and constraining boundary conditions, and selecting a proper computing unit;
step 104: establishing a finite element discrete model according to the geometric model, and dividing grids to form a numerical model;
when the grid is divided, coarsening a stress slow change area and refining a stress rapid change area;
step 105: determining an analysis solving method aiming at the calculation purpose, and calculating the time step length under the conditions of meeting the convergence, the calculation precision and the computer resources;
the analysis solving method comprises the following steps: a static force analysis method and a kinetic force analysis method;
step 106: solving and calculating the numerical model to obtain deformation calculation results at different moments;
step 107: analyzing the grid quality and sensitivity to ensure the accuracy of grid division;
the step 101-107 realizes the establishment of a numerical model for the nuclear power equipment and the numerical calculation to obtain a numerical calculation result.
Step 108: extracting an equipment installation surface with precision requirements according to design input of nuclear power equipment, and determining geometric characteristic elements of the installation surface;
step 109: defining a reference standard for precision evaluation;
step 110: extracting the node deformation displacement information of the geometric characteristic elements of the installation surface of the nuclear power equipment from the numerical calculation result;
step 111: determining the requirement of precision evaluation aiming at the precision characteristic requirement of the installation surface of the nuclear power equipment, and establishing a precision characteristic evaluation model;
wherein, the precision characteristic evaluation model comprises: a shape accuracy model, a direction accuracy model, a position accuracy model, and a run-out accuracy model.
The shape precision model comprises a straightness precision characteristic, a flatness precision characteristic, a roundness precision characteristic, a cylindricity precision characteristic, a line profile precision characteristic and a surface profile precision characteristic;
the direction precision model comprises a parallelism precision characteristic, a perpendicularity precision characteristic and an inclination precision characteristic;
the position precision model comprises a position precision characteristic, a concentricity precision characteristic, a coaxiality precision characteristic and a symmetry precision characteristic;
the run-out precision model comprises a circular run-out precision characteristic and a full run-out precision characteristic.
Step 112: performing data fitting on the deformation elements by adopting a least square method, and performing fitting element parameter identification at different moments;
step 113: calculating the precision of the equipment installation surface at different moments, namely the precision characteristic, according to the precision characteristic evaluation model;
as shown in fig. 2, the accuracy extraction position 1 is shown in the figure, the solid line is an actual profile curve of the evaluation position, the dotted line is a fitted profile obtained by the least square method, d1 and d2 are distances from both sides of the actual profile curve to the fitted profile, respectively, and the sum of the two is the accuracy characteristic.
Step 114: judging whether the calculation precision characteristics meet the requirements of design input, if not, returning to a geometric physical model of nuclear power equipment, modifying and recalculating;
step 115: if the requirements are met, finishing the calculation, inputting a calculation result and forming a calculation report.
In conclusion, the invention solves the problem of precision analysis in the design process of nuclear power equipment. The invention relates to a convenient post-processing method of numerical calculation software, wherein an accuracy characteristic analysis method is used as an extension of the design stress analysis and evaluation of nuclear power equipment, an accuracy characteristic analysis module program is added in the numerical calculation software, the deformation data of a mounting surface in the research and development process can be specified, and technical support is provided for the accuracy design, so that the research and development efficiency and quality of the nuclear power equipment are effectively improved.
Finally, it should also be noted that, herein, relational terms such as first and second, and the like may be used solely to distinguish one entity or action from another entity or action without necessarily requiring or implying any actual such relationship or order between such entities or actions. Also, the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or apparatus. Without further limitation, an element defined by the phrase "comprising an … …" does not exclude the presence of other identical elements in a process, method, article, or apparatus that comprises the element.
The embodiments in the present description are described in a progressive manner, each embodiment focuses on differences from other embodiments, and the same and similar parts among the embodiments are referred to each other.
The previous description of the disclosed embodiments is provided to enable any person skilled in the art to make or use the present invention. Various modifications to these embodiments will be readily apparent to those skilled in the art, and the generic principles defined herein may be applied to other embodiments without departing from the spirit or scope of the invention. Thus, the present invention is not intended to be limited to the embodiments shown herein but is to be accorded the widest scope consistent with the principles and novel features disclosed herein.

Claims (7)

1. A nuclear power equipment design method based on numerical analysis deformation data is characterized by comprising the following steps: the method comprises the following steps:
step 1: establishing a numerical model for nuclear power equipment and carrying out numerical calculation to obtain a numerical calculation result;
step 2: extracting an equipment installation surface with precision requirements according to design input of nuclear power equipment, and determining geometric characteristic elements of the equipment installation surface;
and step 3: defining a reference standard for precision evaluation;
and 4, step 4: extracting node deformation displacement information of geometric characteristic elements of the installation surface of the nuclear power equipment from the numerical calculation result;
and 5: determining the requirement of precision evaluation aiming at the precision characteristic requirement of the installation surface of the nuclear power equipment, and establishing a precision characteristic evaluation model;
step 6: performing data fitting on the deformation elements by adopting a least square method, and performing fitting element parameter identification at different moments;
and 7: calculating the precision characteristics of equipment installation surfaces at different moments according to the precision characteristic evaluation model;
and 8: judging whether the precision characteristic meets the requirement of a precision allowable value of the structural design, if the precision characteristic does not meet the requirement, returning to the step 1, modifying the numerical model and carrying out numerical calculation again;
and step 9: and if the precision characteristic meets the requirement, finishing the calculation, outputting a calculation result and forming a calculation report.
2. The method of claim 1, wherein: the accuracy characteristic evaluation model includes: a shape accuracy model, a direction accuracy model, a position accuracy model, and a run-out accuracy model.
3. The method of claim 2, wherein: the shape precision model comprises a straightness precision characteristic, a flatness precision characteristic, a roundness precision characteristic, a cylindricity precision characteristic, a line profile precision characteristic and a surface profile precision characteristic;
the direction precision model comprises a parallelism precision characteristic, a perpendicularity precision characteristic and an inclination precision characteristic;
the position precision model comprises a position precision characteristic, a concentricity precision characteristic, a coaxiality precision characteristic and a symmetry precision characteristic;
the run-out precision model comprises a circular run-out precision characteristic and a full run-out precision characteristic.
4. The method of claim 1, wherein: the step 1 comprises the following steps:
step A: extracting the precision geometric tolerance requirement of each equipment mounting surface according to the design input of the nuclear power equipment, and taking the precision geometric tolerance requirement as a permissible value of the structural design precision;
and B: inputting a drawing according to the design of nuclear power equipment, and establishing a geometric model;
and C: inputting material attributes of nuclear power equipment, applying mechanical, thermal load and constraint boundary conditions, and determining a calculation unit;
step D: establishing a finite element discrete model according to the geometric model, and dividing grids to form a numerical model;
step E: determining an analysis solving method aiming at the calculation purpose, and calculating the time step length under the conditions of meeting the convergence, the calculation precision and the computer resources;
step F: solving and calculating the numerical model to obtain deformation calculation results at different moments;
step G: and analyzing the grid quality and sensitivity to ensure the accuracy of grid division.
5. The method of claim 4, wherein: and step B, simplifying the geometric model, and considering the detailed characteristics of the geometric model according to the edges, the small bosses and the small grooves of the structure on the premise of ensuring the finite element analysis precision of the concerned part.
6. The method of claim 4, wherein: and D, coarsening a stress slow change area and refining a stress rapid change area when the grid is divided.
7. The method of claim 4, wherein: the analysis solving method comprises a static analysis method and a dynamic analysis method.
CN202011615181.0A 2020-12-30 2020-12-30 Nuclear power equipment design method based on numerical analysis deformation data Pending CN112613148A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202011615181.0A CN112613148A (en) 2020-12-30 2020-12-30 Nuclear power equipment design method based on numerical analysis deformation data

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202011615181.0A CN112613148A (en) 2020-12-30 2020-12-30 Nuclear power equipment design method based on numerical analysis deformation data

Publications (1)

Publication Number Publication Date
CN112613148A true CN112613148A (en) 2021-04-06

Family

ID=75249772

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202011615181.0A Pending CN112613148A (en) 2020-12-30 2020-12-30 Nuclear power equipment design method based on numerical analysis deformation data

Country Status (1)

Country Link
CN (1) CN112613148A (en)

Citations (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN1147889A (en) * 1994-05-13 1997-04-16 明尼苏达州采矿制造公司 Automated image quality control
JPH1153347A (en) * 1997-08-07 1999-02-26 Hitachi Ltd Analyzer
CN102122311A (en) * 2011-02-21 2011-07-13 北京航空航天大学 Method for generating accelerated stability profile of dynamically tuned gyro based on finite element
CN102184289A (en) * 2011-05-06 2011-09-14 大连船舶重工集团装备制造有限公司 Method for carrying out stress analysis on first-class nuclear reactors through using ANSYS software
KR20130085211A (en) * 2012-01-19 2013-07-29 삼성중공업 주식회사 System and method for evaluating correlation of production with welding distortion
CN103345545A (en) * 2013-06-14 2013-10-09 北京航空航天大学 Method for predicating composite material Pi-shaped non-planar glue joint strength based on triangular envelopes
CN103886166A (en) * 2014-04-22 2014-06-25 哈尔滨工业大学 Efficient machining method blending additive manufacturing and removal machining based on geometrical characteristic decomposition of part structures
CN105138731A (en) * 2015-07-27 2015-12-09 中国海洋石油总公司 System and method for evaluating submarine slope instability caused by hydrate decomposition
CN106934176A (en) * 2017-03-30 2017-07-07 上海核工程研究设计院 Processing platform before and after a kind of nuclear power station pipeline automated analysis
CN107729621A (en) * 2017-09-20 2018-02-23 北京安怀信科技股份有限公司 A kind of verification tool of statical model
CN108170924A (en) * 2017-12-21 2018-06-15 西安交通大学 One kind is for Steam Generators in NPP heat transfer pipe plug stream condition model method for building up
CN108614922A (en) * 2018-04-04 2018-10-02 南京航空航天大学 A kind of computational methods of the plate shell edge effect based on the post-processing of stress hybridizationization
CN109522663A (en) * 2018-11-27 2019-03-26 济南大学 A kind of turbine rotor creep impairment real-time computing technique based on finite element model
CN110096760A (en) * 2019-04-10 2019-08-06 西北工业大学 A kind of method for numerical simulation of workpiece thermal deformation
CN110852000A (en) * 2018-07-24 2020-02-28 上汽通用五菱汽车股份有限公司 Vehicle body structure optimization method
CN110941923A (en) * 2019-11-22 2020-03-31 汉思科特(盐城)减震技术有限公司 Method for determining sensitive parameters of air spring structure
CN111605199A (en) * 2020-05-21 2020-09-01 哈尔滨理工大学 Finite element analysis and forming precision method for FDM3D printer
CN111639448A (en) * 2020-05-06 2020-09-08 西北工业大学 Linear friction welding numerical simulation method introducing initial defects

Patent Citations (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN1147889A (en) * 1994-05-13 1997-04-16 明尼苏达州采矿制造公司 Automated image quality control
JPH1153347A (en) * 1997-08-07 1999-02-26 Hitachi Ltd Analyzer
CN102122311A (en) * 2011-02-21 2011-07-13 北京航空航天大学 Method for generating accelerated stability profile of dynamically tuned gyro based on finite element
CN102184289A (en) * 2011-05-06 2011-09-14 大连船舶重工集团装备制造有限公司 Method for carrying out stress analysis on first-class nuclear reactors through using ANSYS software
KR20130085211A (en) * 2012-01-19 2013-07-29 삼성중공업 주식회사 System and method for evaluating correlation of production with welding distortion
CN103345545A (en) * 2013-06-14 2013-10-09 北京航空航天大学 Method for predicating composite material Pi-shaped non-planar glue joint strength based on triangular envelopes
CN103886166A (en) * 2014-04-22 2014-06-25 哈尔滨工业大学 Efficient machining method blending additive manufacturing and removal machining based on geometrical characteristic decomposition of part structures
CN105138731A (en) * 2015-07-27 2015-12-09 中国海洋石油总公司 System and method for evaluating submarine slope instability caused by hydrate decomposition
CN106934176A (en) * 2017-03-30 2017-07-07 上海核工程研究设计院 Processing platform before and after a kind of nuclear power station pipeline automated analysis
CN107729621A (en) * 2017-09-20 2018-02-23 北京安怀信科技股份有限公司 A kind of verification tool of statical model
CN108170924A (en) * 2017-12-21 2018-06-15 西安交通大学 One kind is for Steam Generators in NPP heat transfer pipe plug stream condition model method for building up
CN108614922A (en) * 2018-04-04 2018-10-02 南京航空航天大学 A kind of computational methods of the plate shell edge effect based on the post-processing of stress hybridizationization
CN110852000A (en) * 2018-07-24 2020-02-28 上汽通用五菱汽车股份有限公司 Vehicle body structure optimization method
CN109522663A (en) * 2018-11-27 2019-03-26 济南大学 A kind of turbine rotor creep impairment real-time computing technique based on finite element model
CN110096760A (en) * 2019-04-10 2019-08-06 西北工业大学 A kind of method for numerical simulation of workpiece thermal deformation
CN110941923A (en) * 2019-11-22 2020-03-31 汉思科特(盐城)减震技术有限公司 Method for determining sensitive parameters of air spring structure
CN111639448A (en) * 2020-05-06 2020-09-08 西北工业大学 Linear friction welding numerical simulation method introducing initial defects
CN111605199A (en) * 2020-05-21 2020-09-01 哈尔滨理工大学 Finite element analysis and forming precision method for FDM3D printer

Similar Documents

Publication Publication Date Title
Frepoli An overview of Westinghouse realistic large break LOCA evaluation model
CN103488838A (en) Computer-assisted plotting method for waste heat boiler pipes
Sharabi et al. Computational fluid dynamics study of pressurized thermal shock phenomena in the reactor pressure vessel
Megalingam et al. Comparative contact analysis study of finite element method based deterministic, simplified multi-asperity and modified statistical contact models
Wen et al. A reconstruction and contact analysis method of three-dimensional rough surface based on ellipsoidal asperity
CN202093517U (en) Device utilizing universal program ANSYS to calculate cooling tower
Craig McClung et al. New methods for automated fatigue crack growth and reliability analysis
CN105810254A (en) Restarting method and system for making few-group cross section used in reactor nuclear design
Du et al. Optimal design of fixture layout for compliant part with application in ship curved panel assembly
CN109299563B (en) Boiler steel structure space detection method based on NX three-dimensional design software
Ohshima et al. ARKADIA—For the Innovation of Advanced Nuclear Reactor Design
CN110909501A (en) Method for calculating load amplification factor in system dynamic analysis
CN112613148A (en) Nuclear power equipment design method based on numerical analysis deformation data
CN102129483A (en) Method for automatically generating test vector of design rule checking (DRC) rule file
CN110390174B (en) Method and device for optimizing and selecting steel structure of thickener
Wang et al. Analysis of focusing effect of light metallic layer in stratified molten pool under IVR-ERVC condition
Liu et al. Aerodynamic and mechanical analyses on manufacturing variations of a turbine blade row
Jewer et al. An immersed body method for coupled neutron transport and thermal hydraulic simulations of PWR assemblies
Qian et al. Probabilistic Pressurized Thermal Shock Analysis for a Reactor Pressure Vessel Considering Plume Cooling Effect
Imron et al. Pressurized water reactor mixed Oxide/UO2 transient benchmark calculations using Monte Carlo Serpent 2 code and open nodal core simulator ADPRES
Mohanty et al. Implementation of ANL’s Mechanics Based Evolutionary Fatigue Modeling Through ABAQUS-WARP3D Based High-Performance Computing Framework
Wang et al. Characters of neutron noise in full-size molten salt reactor
Gonzalez-Amoros et al. Capability Extension of the High-Resolution Thermal-Hydraulic Code ESCOT for Hexagonal Geometry Core Multiphysics Analysis
CN111931313B (en) Method, device, equipment and medium for processing overrun structure
Takeuchi et al. MULTIFLEX: a FORTRAN-IV Computer Program for analyzing thermal-hydraulic-structure system dynamics.[PWR]

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