• Title/Summary/Keyword: commercial computer code

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Development of Fashion Design Applying Code and Tape Trimming Decoration Techniques of Computer Embroidery Machine (컴퓨터 자수기계 코드 및 테이프 트리밍 장식기법을 활용한 패션디자인 개발)

  • Seoyun, Lee;Jiyoung, Kim
    • Journal of Fashion Business
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    • v.26 no.5
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    • pp.1-21
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    • 2022
  • Purpose of this study is to develop fashion design with greater added value and to seek the expandability of its expression domain by applying special computer code and tape embroidery machine capable of creating more special and fancier fashion to the development of fashion design by focusing on the fashion decorations that are becoming increasingly more computer systematized. For this purpose, expression techniques and effects of computer embroidery machine code and tape trimming decoration techniques, and cases of modern fashion design are examined. Major images are then deduced to designing and production of actual 6 creative pieces equipped with creativity and commercial value by applying such images deduced. As the results, it is not only possible to develop highly value added fashion design by utilizing mixed computer embroidery machine code and tape trimming decoration technique but also to produce countlessly new and unique surfaces by inducing changes in diversified pattern expressions, thickness of cord thread, and width, color and texture of material, etc. of the tape. This can maximize the expression domain of design, and fulfill the fashion desires of consumers wanting modern enhancement of quality and individualization. If multilateral attempts and studies for the aforementioned purposes can be expanded continuously, it is deemed possible to broaden the range of expression techniques in fashion design and, moreover, to make contribution towards enhancement of competitiveness of fashion industry.

A Study on Sunshine Environment with Different Distance between Buildings (인동간격에 따른 일조환경에 대한 연구)

  • 최용석;최지혜;김용식
    • Journal of the Korean housing association
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    • v.15 no.2
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    • pp.55-62
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    • 2004
  • Apartment design in residential Area is restricted by building distance limit code. Building distance limit decreases gradually to the 0.8H(height), and residential area has 250% site area ratio by building code, so site using has become efficient. In this study, examine the relationship between present building distance limit and right of daylighting environment by computer simulation. As well, high-rise residential officetel and multipurpose residential building becomes increase in commercial non-residential area. In the domestic, residential type multipurpose building made at the business area or central business area has 400∼800% site area ratio by building code. However, at a dweller's point of view, there are much lacks of environmental consideration to provide suitable daylighting environment. And, POE: Post Occupancy Evaluation is not completed yet. In this study, however, progress architectural environment prediction, basis by right of daylighting, and examine the possibility of daylighting by architectural distance limit code in residental area and by high-rise, high-density residential building in non-residental downtown area.

Modeling and simulation of VERA core physics benchmark using OpenMC code

  • Abdullah O. Albugami;Abdullah S. Alomari;Abdullah I. Almarshad
    • Nuclear Engineering and Technology
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    • v.55 no.9
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    • pp.3388-3400
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    • 2023
  • Detailed analysis of the neutron pathway through matter inside the nuclear reactor core is exceedingly needed for safety and economic considerations. Due to the constant development of high-performance computing technologies, neutronics analysis using computer codes became more effective and efficient to perform sophisticated neutronics calculations. In this work, a commercial pressurized water reactor (PWR) presented by Virtual Environment for Reactor Applications (VERA) Core Physics Benchmark are modeled and simulated using a high-fidelity simulation of OpenMC code in terms of criticality and fuel pin power distribution. Various problems have been selected from VERA benchmark ranging from a simple two-dimension (2D) pin cell problem to a complex three dimension (3D) full core problem. The development of the code capabilities for reactor physics methods has been implemented to investigate the accuracy and performance of the OpenMC code against VERA SCALE codes. The results of OpenMC code exhibit excellent agreement with VERA results with maximum Root Mean Square Error (RMSE) values of less than 0.04% and 1.3% for the criticality eigenvalues and pin power distributions, respectively. This demonstrates the successful utilization of the OpenMC code as a simulation tool for a whole core analysis. Further works are undergoing on the accuracy of OpenMC simulations for the impact of different fuel types and burnup levels and the analysis of the transient behavior and coupled thermal hydraulic feedback.

Automated Structural Design System Using Fuzzy Theory and Neural Network

  • Lee, Joon-Seong
    • International Journal of Precision Engineering and Manufacturing
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    • v.3 no.1
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    • pp.43-48
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    • 2002
  • This paper describes an automated computer-aided engineering (CAE) system for three-dimensional structures. An automatic finite element mesh-generation technique, which is based on fuzzy knowledge processing and computational geometry techniques, is incorporated into the system, together with a commercial FE analysis code, and a commercial solid modeler. The system allows a geometry model of interest to be automatically converted to different FE models, depending on the physical phenomena of the structures to be analyzed, i.e., electrostatic analysis, stress analysis, modal analysis, and so on. Also, with the aid of multilayer neural networks, the present system allows us to obtain automatically a design window in which a number of satisfactory design solutions exist in a multi-dimensional design parameter space. The developed CAE system is successfully applied to evaluate an electrostatic micromachines.

Automated CAE Evaluation of Electrostatic Micro Actuator (정전 마이크로 액츄에이터의 자동 CAE 평가)

  • Lee, Joon-Seong
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 1996.11a
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    • pp.711-715
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    • 1996
  • This paper describes an automated computer-aided engineering (CAE) system for micromachines whose size range 10 to 10$^3$${\mu}{\textrm}{m}$. An automatic finite element mesh generation technique, which is based on the fuzzy knowledge processing and computational geometry techniques, is incorporated into the system, together with one of commercial finite clement (FE) analysis codes, MARC, and one of commercial solid modelers, Designbase. The system allows a geometry model of concern to be a automatically converted to different FE models, depending on physical phenomena to be analyzed, i.e. electrostatic analysis, stress analysis, modal analysis and so on. The FE analysis models are then exported to the FE analysis code, and then analyses are performed. This system is successfully applied to an electrostatic micro actuator.

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Parallel Procedure and Evaluation of Parallel Performance of Impact Simulation Based on Two-Step Eulerian Scheme (Two-Step Eulerian 기법에 기반 한 충돌 해석의 병렬처리 및 병렬효율 평가)

  • Kim Seung-Jo;Lee Min-Hyung;Paik Seung-Hoon
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.30 no.10 s.253
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    • pp.1320-1327
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    • 2006
  • Parallel procedure and performance of two-step Eulerian code have not been reported sufficiently yet even though it was developed and utilized widely in the impact simulation. In this study, parallel strategy of two-step Eulerian code was proposed and described in detail. The performance was evaluated in the self-made linux cluster computer. Compared with commercial code, a relatively good performance is achieved. Through the performance evaluation of each computation stage, remap is turned out to be the most time consuming part among the other part such as FE processing, communication, time marching etc.

COSMOS : A Computer Code for the Analysis of LWR $UO_2$ and MOX Fuel Rod

  • Koo, Yang-Hyun;Lee, Byung-Ho;Sohn, Dong-Seong
    • Nuclear Engineering and Technology
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    • v.30 no.6
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    • pp.541-554
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    • 1998
  • A computer code COSMOS has been developed based on the CARO-D5 for the thermal analysis of LWR UO$_2$ and MOX fuel rod under steady-state and transient operating conditions. The main purpose of the COSMOS, which considers high turnup characteristics such as thermal conductivity degradation with turnup and rim formation at the outer part of fuel pellet, is to calculate temperature profile across fuel pellet and fission gas release up to high burnup. A new mechanistic fission gas release model developed based on physical processes has been incorporated into the code. In addition, the features of MOX fuel such as change in themo-mechanical properties and the effect of microscopic heterogeneity on fission gas release have been also taken into account so that it can be applied to MOX fuel. Another important feature of the COSMOS is that it can analyze fuel segment refabricated from base irradiated fuel rods in commercial reactors. This feature makes it possible to analyze database obtained from international projects such as the MALDEN and RISO, many of which were collected from refabricated fuel segments. The capacity of the COSMOS has been tested with some number of experimental results obtained from the HALDEN, RISO and FIGARO programs. Comparison with the measured data indicates that, although the COSMOS gives reasonable agreement, the current models need to be improved. This work is being performed using database available from the OECD/NEA.

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Comparative Study of Finite Element Analysis for Stresses Occurring in Various Models of the Spent Nuclear Fuel Disposal Canister due to the Accidental Drop and Impact on to the Ground (추락낙하 사고 시 지면과의 충돌충격에 의하여 다양한 고준위폐기물 처분용기모델에 발생하는 응력에 대한 유한요소해석 비교연구)

  • Kwon, Young-Joo
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.30 no.5
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    • pp.415-425
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    • 2017
  • Stresses occur in the spent nuclear fuel disposal canister due to the impulsive forces incurred in the accidental drop and impact event from the transportation vehicle onto the ground during deposition in the repository. In this paper, the comparative study of finite element analysis for stresses occurring in various models of the spent nuclear fuel disposal canister due to these impulsive forces is presented as one of design processes for the structural integrity of the canister. The main content of the study is about the design of the structurally safe canister through this comparative study. The impulsive forces applied to the canister subjected to the accidental drop and impact event from the transportation vehicle onto the ground in the repository are obtained using the commercial rigid body dynamic analysis computer code, RecurDyn. Stresses and deformations occurring due to these impulsive forces are obtained using the commercial finite element analysis computer code, NISA. The study for the structurally safe canister is carried out thru comparing and reviewing these values. The study results show that stresses become larger as the wall encompassing the spent nuclear fuel bundles inside the canister becomes thicker or as the diameter of the canister becomes larger. However, the impulsive force applied to the canister also becomes larger as the canister diameter becomes larger. Nonetheless, the deformation value per unit impulsive force decreases as the canister diameter increases. Therefore, conclusively the canister is structurally safe as the diameter increases.

Nonlinear Structural Analysis of the Spent Nuclear Fuel Disposal Canister Subjected to an Accidental Drop and Ground Impact Event (추락낙하 사고 시 지면과 충돌하는 고준위폐기물 처분용기의 비선형구조해석)

  • Kwon, Young-Joo
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.32 no.2
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    • pp.75-86
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    • 2019
  • The biggest obstacle in the nuclear power generation is the high level radioactive waste such as the spent nuclear fuel. High level radioactivities and generated heat make the safe treatment of the spent nuclear fuel very difficult. Nowadays, the only treatment method is a deep geological disposal technology. This paper treats the structural safe design problem of the spent nuclear fuel disposal canister which is one of the core technologies of the deep geological disposal technology. Especially, this paper executed the nonlinear structural analysis for the stresses and deformations occurring in the canister due to the impulsive force applied to the spent nuclear fuel disposal canister in the case of an accidental drop and ground impact event from the transportation vehicle in the repository. The main content of the analysis is about that the impulsive force is obtained using the commercial rigid body dynamic analysis computer code, RecurDyn, and the stress and deformation caused by this impulsive force are obtained using the commercial finite element static structural analysis computer code, NISA. The analysis results show that large stresses and deformations may occur in the canister, especially in the rid or the bottom of the canister, due to the impulsive force occurring during the collision impact period.

A Study on the Defect Formation in Conform Process (CONFORM공정에서의 결함생성에 관한 연구)

  • 김영호;조진래;곽인섭
    • Proceedings of the Korean Society of Precision Engineering Conference
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    • 1995.10a
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    • pp.210-213
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    • 1995
  • In this study,the effect of both process parameters (wheel velocity, friction coefficients between die and billet, etc) and die-shape (abutment height and shape, flash gap, etc.) on the surface defect on forming process is theoretically investigated. For this work, computer simulation was performed by using the DEFORM, a commercial FEM code. Through numerous simulations with different parameters and die shapes, We propose one optimal die shape for CONFORM process which can remove surface defect.

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