• Title/Summary/Keyword: Engineering calculation

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Dose Calculation of Photon Beam with Wedge Filter for Radiation Therapy Planning System

  • Cheong, Kwang-Ho;Suh, Tae-Suk;Lee, Hyoung-Koo;Choe, Bo-Young
    • Proceedings of the Korean Society of Medical Physics Conference
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    • 2003.09a
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    • pp.41-41
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    • 2003
  • Purpose: Even if the wedge filter is widely used for the radiation therapy to modify the photon beam intensity, the wedged photon beam dose calculation is not so easy. Radiation therapy planning systems (RTPS) have been used the empirical or semi-analytical methods such as attenuation method using wedge filter parameters or wedge filter factor obtained from measurement. However, these methods can cause serious error in penumbra region as well as in edge region. In this study, we propose the dose calculation algorithm for wedged field to minimize the error especially in the outer beam region. Materials and Method: Modified intensity by wedge filter was calculated using tissue-maximum ratio (TMR) and scatter-maximum ratio (SMR) of wedged field. Profiles of wedged and non-wedged direction was also used. The result of new dose calculation was compared with measurement and the result from attenuation method. Results: Proposed algorithm showed the good agreement with measurement in the high dose-gradient region as well as in the inner beam region. The error was decreased comparing to attenuation method. Conclusion: Although necessary beam data for the RTPS commissioning was increased, new algorithm would guarantee the improved dose calculation accuracy for wedged field. In future, this algorithm could be adopted in RTPS.

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Verification of neutronics and thermal-hydraulic coupled system with pin-by-pin calculation for PWR core

  • Zhigang Li;Junjie Pan;Bangyang Xia;Shenglong Qiang;Wei Lu;Qing Li
    • Nuclear Engineering and Technology
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    • v.55 no.9
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    • pp.3213-3228
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    • 2023
  • As an important part of the digital reactor, the pin-by-pin wise fine coupling calculation is a research hotspot in the field of nuclear engineering in recent years. It provides more precise and realistic simulation results for reactor design, operation and safety evaluation. CORCA-K a nodal code is redeveloped as a robust pin-by-pin wise neutronics and thermal-hydraulic coupled calculation code for pressurized water reactor (PWR) core. The nodal green's function method (NGFM) is used to solve the three-dimensional space-time neutron dynamics equation, and the single-phase single channel model and one-dimensional heat conduction model are used to solve the fluid field and fuel temperature field. The mesh scale of reactor core simulation is raised from the nodal-wise to the pin-wise. It is verified by two benchmarks: NEACRP 3D PWR and PWR MOX/UO2. The results show that: 1) the pin-by-pin wise coupling calculation system has good accuracy and can accurately simulate the key parameters in steady-state and transient coupling conditions, which is in good agreement with the reference results; 2) Compared with the nodal-wise coupling calculation, the pin-by-pin wise coupling calculation improves the fuel peak temperature, the range of power distribution is expanded, and the lower limit is reduced more.

EXAMINATION OF CALCULATION METHOD FOR THE FLEXURAL RIGIDITY OF CROP STALKS

  • Hirai, Yasumaru;Inoue, Eiji;Hashiguchi, Koichi;Kim, Young-Keun;Inaba, Shigeki;Tashiro, Katsumi
    • Proceedings of the Korean Society for Agricultural Machinery Conference
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    • 2000.11b
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    • pp.287-294
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    • 2000
  • Calculation of the flexural rigidity value (EI) is indispensable for prescription of deflection characteristics of crop stalks in harvesting□Conventionally□EI has been determined by either average EI of the whole stalk or average EI of each stems divided into node through the calculation method of cantilever with homogeneous section□However□deflection characteristics of crop stalks caused by mechanical operation such as combine harvester were not exactly presumed by these conventional EI through the experiment by authors. Further, actual EI of a stalk changes in company with a change of moisture contents as time passes during the experiment. Finally, efficient calculation method for determining EI is needed in order to improve these problems. In this study, mechanical model based on actual structure of the crop stalk with variety sectional area was proposed. This mechanical model is calculated by the theory of cantilever with continuous stages. Therefore, improvement of both calculating accuracy on EI and efficiency of measuring system was tried. At first, this calculation method was applied to piano wire of which EI was recognized in advance. As a result, EI calculated from this new method coincided approximately with piano wire's EI. Next, applying to crop stalks as same as piano wire, relationship between loads acting on crop stalks and deflection values calculated by EI using this new calculation method was exactly presumed in comparison with conventional method. Further, measuring time of deflection test was greatly reduced. Finally, new calculation method of EI will be available for estimating mechanical characteristics of so many kinds of crop stalks in harvesting operation. Further, in this study, new deflection test using image-processing apparatus by computer will be introduced.

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Development of supporting platform for the fine flow characteristics of reactor core

  • Hao Qian;Guangliang Chen;Lei Li;Lixuan Zhang;Xinli Yin;Hanqi Zhang;Shaomin Su
    • Nuclear Engineering and Technology
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    • v.56 no.5
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    • pp.1687-1697
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    • 2024
  • This study presents the Supporting platform for reactor fine flow characteristics calculation and analysis (Cilian platform), a user-friendly tool that supports the analysis and optimization of pressurized water reactor (PWR) cores with mixing vanes using computational fluid dynamics (CFD) computing. The Cilian platform allows for easy creation and optimization of PWR's main CFD calculation schemes and autonomously manages CFD calculation and analysis of PWR cores, reducing the need for human and computational resources. The platform's key features enable efficient simulation, rapid solution design, automatic calculation of core scheme options, and streamlined data extraction and processing techniques. The Cilian platform's capability to call external CFD software reduces the development time and cost while improving the accuracy and reliability of the results. In conclusion, the Cilian platform exemplifies an innovative solution for efficient computational fluid dynamics analysis of pressurized water reactor (PWR) cores. It holds great promise for driving advancements in nuclear power technology, enhancing the safety, efficiency, and cost-effectiveness of nuclear reactors. The platform adopts a modular design methodology, enabling the swift and accurate computation and analysis of diverse flow regions within core components. This design approach facilitates the seamless integration of multiple computational modules across various reactor types, providing a high degree of flexibility and reusability.

Loop Current Calculation based on Voltage Angle Difference at Tie Switch for Switching Plan Validation in Distribution System Operation (상시개방점 양단전압 측정값을 이용한 배전선로 루프운전 가능 여부 판단 방법)

  • Son, Juhwan;Lim, Seongil
    • Journal of the Korean Institute of Illuminating and Electrical Installation Engineers
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    • v.29 no.7
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    • pp.14-21
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    • 2015
  • Distribution systems are operated in radial structure, but temporal loop structure could be founded the live load transfer. Main purposes of reconfiguration of distribution network are load balancing, loss minimization and voltage drop maintaining. In the loop structure, huge loop current can be flowed between two substations in case of large voltage angle difference. Protection devices of distribution line can be triped by this huge loop current. So, precise calculation of loop current is very important for secure switching. This paper proposes a novel calculation method of loop current using the voltage angle differences measured at the tie switches. Feasibility of the propose method has been verified by various case studies based on Matlab simulation.

A Study on Limiting Factor of Capital Assets Investment Calculation (경제성공학의 한계에 관한 고찰)

  • 김성집
    • Journal of Korean Society of Industrial and Systems Engineering
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    • v.2 no.2
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    • pp.5-10
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    • 1979
  • For investment calculation of capital assets, it is desirable to grasp the limiting factors of its calculation. The limiting factors can be listed as follows; $\circled1$ difficulty in estimating the service life of capital assets. $\circled2$ difficulty in estimating the receipts, and operating and maintenance expenses of the project. $\circled3$ difficulty in determining common Minimum Attractive Rate of Return. $\circled4$ difficulty in estimating the salvage value of the assets. $\circled5$ some limiting factors on present worth calculation of the projects. $\circled6$ Some limiting factors on payout period method of the economic calculation.

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A Method for Automatic Check of Omitted Design Item in Structural Calculation Document of Steel Box Bridges (강박스 교량을 대상으로 한 구조계산서의 누락된 설계항목 검토 자동화 방법론)

  • Park, Sang-Il;An, Hyun-Jung;Kim, Bong-Geun;Lee, Sang-Ho
    • Proceedings of the Computational Structural Engineering Institute Conference
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    • 2007.04a
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    • pp.813-818
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    • 2007
  • A method for automatic check of omitted design item in structural calculation document of steel box bridges is proposed. A method for automatic check of omitted design item in structural calculation document of steel box bridges is proposed. Information processing for the proposed method is divided into two steps: automatic generation of document structure in XML Schema Definition (XSD) format and extract omitted design items by using the XML Schema matching technique. The automatic omitted element filter is developed on the basis of the proposed method, and the accuracy of the developed module is examined with case study subjected to existing structural calculation document samples.

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Nonlinear analysis of the influence of increments amounts and history load on soil response

  • Ivandic, Kreso;Soldo, Bozo
    • Structural Engineering and Mechanics
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    • v.33 no.1
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    • pp.67-77
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    • 2009
  • The soil response calculation is described, by which, threw the fictive path of stress, the stress-deformation diagrams are determined, considering the nonlinear soil behavior. The calculation are lead incrementally, by which is shown that in the presented soil model (modified Cam Clay), considering the influence of overconsolidated soil pressure OCR, the number of calculation steps may, but not necessarily, have a sufficient influence on the value of failure load and definite soil deformation. The simplicity and the practicalness of the procedure, the enables modeling the complex relations in soil.

Torque Calculation Method of a Permanent Magnet Spherical Motor

  • Lee, Hyung-Woo;Kang, Dong-Woo;Lee, Ju
    • Journal of Electrical Engineering and Technology
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    • v.5 no.3
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    • pp.431-434
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    • 2010
  • This paper presents the torque calculation method of a permanent magnet spherical motor. To calculate using the finite element method (FEM), three-dimensional (3D) FEM must be used. However, since the method requires excessive time and memory, an easier torque calculation method is hereby presented. In the proposed method, it is very important to obtain the approximation function of the torque profile curve. We present the approximation method of the torque profile curve and show that the torque calculation result can approximate the torque obtained by 3-D FEM.

STRAUM-MATXST: A code system for multi-group neutron-gamma coupled transport calculation with unstructured tetrahedral meshes

  • MyeongHyeon Woo;Ser Gi Hong
    • Nuclear Engineering and Technology
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    • v.54 no.11
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    • pp.4280-4295
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    • 2022
  • In this paper, a new multi-group neutron-gamma transport calculation code system STRAUM-MATXST for complicated geometrical problems is introduced and its development status including numerical tests is presented. In this code system, the MATXST (MATXS-based Cross Section Processor for SN Transport) code generates multi-group neutron and gamma cross sections by processing MATXS format libraries generated using NJOY and the STRAUM (SN Transport for Radiation Analysis with Unstructured Meshes) code performs multi-group neutron-gamma coupled transport calculation using tetrahedral meshes. In particular, this work presents the recent implementation and its test results of the Krylov subspace methods (i.e., Bi-CGSTAB and GMRES(m)) with preconditioners using DSA (Diffusion Synthetic Acceleration) and TSA (Transport Synthetic Acceleration). In addition, the Krylov subspace methods for accelerating the energy-group coupling iteration through thermal up-scatterings are implemented with new multi-group block DSA and TSA preconditioners in STRAUM.