• Title/Summary/Keyword: System Codes

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Multi-core-based Parallel Query of 3D Point Cloud Indexed in Octree (옥트리로 색인한 3차원 포인트 클라우드의 다중코어 기반 병렬 탐색)

  • Han, Soohee
    • Journal of the Korean Society of Surveying, Geodesy, Photogrammetry and Cartography
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    • v.31 no.4
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    • pp.301-310
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    • 2013
  • The aim of the present study is to enhance query speed of large 3D point cloud indexed in octree by parallel query using multi-cores. Especially, it is focused on developing methods of accessing multiple leaf nodes in octree concurrently to query points residing within a radius from a given coordinates. To the end, two parallel query methods are suggested using different strategies to distribute query overheads to each core: one using automatic division of 'for routines' in codes controlled by OpenMP and the other considering spatial division. Approximately 18 million 3D points gathered by a terrestrial laser scanner are indexed in octree and tested in a system with a 8-core CPU to evaluate the performances of a non-parallel and the two parallel methods. In results, the performances of the two parallel methods exceeded non-parallel one by several times and the two parallel rivals showed competing aspects confronting various query radii. Parallel query is expected to be accelerated by anticipated improvements of distribution strategies of query overhead to each core.

A Study on Radioactive Source-term Assessment Method for Decommissioning PWR Primary System (PWR 1차계통내 해체 방사성선원항 평가방법에 관한 연구)

  • Song, Jong Soon;Kim, Hyun-Min;Lee, Sang-Heon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.12 no.2
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    • pp.153-164
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    • 2014
  • Currently, there are many programs which are now being developed or already developed to predict radionuclide and corrosion product at the stage of designing NPP. However, since there are not many developments in evaluating quantity of activation corrosion products occurring when disassembling a nuclear power plant there exist some difficulties in calculating accurately. In order to evaluate activation products inventory for the research of effect of neutron activation in the reactor vessel, component of nuclear reactor and adjacent structures, it should be evaluated by using operation history of nuclear reactor, material composition of structure and average neutron flux in every field representing fixed structure of nuclear reactor. In this study, CORA, PACTOLE, CRUDSIM, CREAT and ACE codes are analyzed to predict the quantity of radionuclide and corrosion product of primary reactor which is used at the stage of designing. As a future study, the accuracy in calculating the quantity of product corrosion can be increase by finding out the possibility of use and improvement for evaluation of the decontamination.

Design and Implementation of a HTMLtoVoiceXML Converter (HTMLtoVoiceXML 변환기의 설계 및 구현)

  • Choi, Hoon-il;Jang, Young-Gun
    • Journal of KIISE:Computing Practices and Letters
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    • v.7 no.6
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    • pp.559-569
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    • 2001
  • It is possible to access web contents by mobile terminals and telephones due to the evolution of voice and VoiceXML technologies. Nevertheless, because these days most of all the web contents are constructed by HTML, it is impossible to access them by using the new technology. Therefore, to access the contents through voices requires the conversion of the web document from HTML to VoiceXML, but its manual conversion process should be involved additional time and expenditure. In this paper, we design and implement HTMLtoVoiceXML converter, suggest a system structure of it and propose a practical identification algorithm of meaningful fragmented group of contents to solve the problem. To test the performance and validity of the converter, we apply it to more than 400 web pages in Korean web sites, it works well except for web pages which involve invalid HTML codes.

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Part1 : Numerical Code Validation and Quantitative Analyses of Ice Accretion around Airfoils (Part1 : 익형 주위 결빙 예측 코드 검증 및 정량적 분석)

  • Son, Chan-Kyu;Oh, Se-Jong;Yee, Kwan-Jung
    • Journal of the Korean Society for Aeronautical & Space Sciences
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    • v.38 no.11
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    • pp.1094-1104
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    • 2010
  • In the previous studies, the validation of numerical codes has been conducted based on the qualitative comparison of predicted ice shapes with experiments, which poses a significant limit on the systematic analysis of ice shapes due to the variation of meteorological conditions. In response to this, the numerical code has been quantitatively validated against available experiment for the ice accretion on cylinders and airfoils in the present study. Ice shapes accumulated on the bodies are systematically investigated with respect to various icing parameters. To this end, maximum thickness, heading direction and ice thickness are quantified and expressed in the polar coordinate system for the comparison with other numerical results. By applying the quantitative analysis, similar shapes are intuitively distinguished. The developed numerical code underestimates the ice accretion area and the ice thickness of lower surface. In order to improve the accuracy, further accurate aerodynamic solver is required for the water droplet trajectories.

Development of a Computer-Assisted Microbiological Quality Assurance Program for Hosipital Foodservice Operations (병원 급식시설의 미생물적 품질관리를 위한 전산 프로그램개발에 관한 연구)

  • Kwak, Tong-Kyung;Jang, Hye-Ja;Joo, Se-Young
    • Korean journal of food and cookery science
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    • v.8 no.2
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    • pp.137-145
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    • 1992
  • A computer-assisted microbiological quality assurance program was developed based on HACCP data obtained from a 500 bed general hospital by assessing time and temperature conditions and microbiological qualities of six categories of menu items according to the process of food product flow. The purpose of the study was to develop a computer-assisted microbiological quality assurance program in order to simplify the assessment procedures and to provide a maximum assurance to foodservice personnel and the public. A 16-Bit personnel computer compatible with IBM-PC/AT was used. The data base files and processing programs were created using dBASE III plus packages. The contents of the computerized system are summarized as knows: 1. When the input program for hazard analysis runs, a series of questions are asked to determine hazards and assess their severity and risks. Critical control points and monitoring methods for CCPs are identified and saved in Master file. 2. Output and search programs for hazard analysis are composed of 6 categories of recipe data file list, code identification list, and HACCP identification of the specific menu item. 3. When the user selects a specific category of recipe from 6 categories presented on the screen and runs data file list, a series of menu item list, CCP list, monitoring methods list are generated. When the code search program runs, menu names, ingredients, amounts and a series of codes are generated. 4. When the user types in a menu item and an identification code, critical control points and monitoring methods are generated for each menu item.

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Design of a Correlator and an Access-code Generator for Bluetooth Baseband (블루투스 기저대역을 위한 상관기와 액세스 코드 생성 모듈의 설계)

  • Hwang Sun-Won;Lee Sang-Hoon;Shin Wee-Jae
    • Journal of the Institute of Convergence Signal Processing
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    • v.6 no.4
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    • pp.206-211
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    • 2005
  • We describe the design for a correlator and an access code generator in bluetooth system. These are used for a connection setting, a packet decision and a clock synchronization between Bluetooth units. The correlator consists of two blocks; carry save adder based on Wallace tree and threshold-value decision block. It determines on an useful packet and clock-synchronization for input signal of 1.0Mbps through the sliding-window correlating. The access-code generator also consists of two blocks; BCH(Bose-Chadhuri-Hocquenghem) cyclic encoder and control block. It generates the access-codes according to four steps' generation process based on Bluetooth standard. In order to solve synchronization problem, we make use of any memory as a pseudo random sequence. The proposed correlator and access-code generator were coded with VHDL. An FPGA Implementation of these modules and the simulation results are proved by Xilinx chip. The critical delay and correlative margin based on synthesis show the 4.689ns and the allowable correlation-error up to 7-bit.

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DNA Barcoding of Fish, Insects, and Shellfish in Korea

  • Kim, Dae-Won;Yoo, Won-Gi;Park, Hyun-Chul;Yoo, Hye-Sook;Kang, Dong-Won;Jin, Seon-Deok;Min, Hong-Ki;Paek, Woon-Kee;Lim, Jeong-Heui
    • Genomics & Informatics
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    • v.10 no.3
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    • pp.206-211
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    • 2012
  • DNA barcoding has been widely used in species identification and biodiversity research. A short fragment of the mitochondrial cytochrome c oxidase subunit I (COI) sequence serves as a DNA bio-barcode. We collected DNA barcodes, based on COI sequences from 156 species (529 sequences) of fish, insects, and shellfish. We present results on phylogenetic relationships to assess biodiversity the in the Korean peninsula. Average GC% contents of the 68 fish species (46.9%), the 59 shellfish species (38.0%), and the 29 insect species (33.2%) are reported. Using the Kimura 2 parameter in all possible pairwise comparisons, the average interspecific distances were compared with the average intraspecific distances in fish (3.22 vs. 0.41), insects (2.06 vs. 0.25), and shellfish (3.58 vs. 0.14). Our results confirm that distance-based DNA barcoding provides sufficient information to identify and delineate fish, insect, and shellfish species by means of all possible pairwise comparisons. These results also confirm that the development of an effective molecular barcode identification system is possible. All DNA barcode sequences collected from our study will be useful for the interpretation of species-level identification and community-level patterns in fish, insects, and shellfish in Korea, although at the species level, the rate of correct identification in a diversified environment might be low.

FLUID-STRUCTURE INTERACTION IN A U-TUBE WITH SURFACE ROUGHNESS AND PRESSURE DROP

  • Gim, Gyun-Ho;Chang, Se-Myoung;Lee, Sinyoung;Jang, Gangwon
    • Nuclear Engineering and Technology
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    • v.46 no.5
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    • pp.633-640
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    • 2014
  • In this research, the surface roughness affecting the pressure drop in a pipe used as the steam generator of a PWR was studied. Based on the CFD (Computational Fluid Dynamics) technique using a commercial code named ANSYS-FLUENT, a straight pipe was modeled to obtain the Darcy frictional coefficient, changed with a range of various surface roughness ratios as well as Reynolds numbers. The result is validated by the comparison with a Moody chart to set the appropriate size of grids at the wall for the correct consideration of surface roughness. The pressure drop in a full-scale U-shaped pipe is measured with the same code, correlated with the surface roughness ratio. In the next stage, we studied a reduced scale model of a U-shaped heat pipe with experiment and analysis of the investigation into fluid-structure interaction (FSI). The material of the pipe was cut from the real heat pipe of a material named Inconel 690 alloy, now used in steam generators. The accelerations at the fixed stations on the outer surface of the pipe model are measured in the series of time history, and Fourier transformed to the frequency domain. The natural frequency of three leading modes were traced from the FFT data, and compared with the result of a numerical analysis for unsteady, incompressible flow. The corresponding mode shapes and maximum displacement are obtained numerically from the FSI simulation with the coupling of the commercial codes, ANSYS-FLUENT and TRANSIENT_STRUCTURAL. The primary frequencies for the model system consist of three parts: structural vibration, BPF(blade pass frequency) of pump, and fluid-structure interaction.

EXPERIMENTAL INVESTIGATIONS RELEVANT FOR HYDROGEN AND FISSION PRODUCT ISSUES RAISED BY THE FUKUSHIMA ACCIDENT

  • GUPTA, SANJEEV
    • Nuclear Engineering and Technology
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    • v.47 no.1
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    • pp.11-25
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    • 2015
  • The accident at Japan's Fukushima Daiichi nuclear power plant in March 2011, caused by an earthquake and a subsequent tsunami, resulted in a failure of the power systems that are needed to cool the reactors at the plant. The accident progression in the absence of heat removal systems caused Units 1-3 to undergo fuel melting. Containment pressurization and hydrogen explosions ultimately resulted in the escape of radioactivity from reactor containments into the atmosphere and ocean. Problems in containment venting operation, leakage from primary containment boundary to the reactor building, improper functioning of standby gas treatment system (SGTS), unmitigated hydrogen accumulation in the reactor building were identified as some of the reasons those added-up in the severity of the accident. The Fukushima accident not only initiated worldwide demand for installation of adequate control and mitigation measures to minimize the potential source term to the environment but also advocated assessment of the existing mitigation systems performance behavior under a wide range of postulated accident scenarios. The uncertainty in estimating the released fraction of the radionuclides due to the Fukushima accident also underlined the need for comprehensive understanding of fission product behavior as a function of the thermal hydraulic conditions and the type of gaseous, aqueous, and solid materials available for interaction, e.g., gas components, decontamination paint, aerosols, and water pools. In the light of the Fukushima accident, additional experimental needs identified for hydrogen and fission product issues need to be investigated in an integrated and optimized way. Additionally, as more and more passive safety systems, such as passive autocatalytic recombiners and filtered containment venting systems are being retrofitted in current reactors and also planned for future reactors, identified hydrogen and fission product issues will need to be coupled with the operation of passive safety systems in phenomena oriented and coupled effects experiments. In the present paper, potential hydrogen and fission product issues raised by the Fukushima accident are discussed. The discussion focuses on hydrogen and fission product behavior inside nuclear power plant containments under severe accident conditions. The relevant experimental investigations conducted in the technical scale containment THAI (thermal hydraulics, hydrogen, aerosols, and iodine) test facility (9.2 m high, 3.2 m in diameter, and $60m^3$ volume) are discussed in the light of the Fukushima accident.

An LDPC Code Replication Scheme Suitable for Cloud Computing (클라우드 컴퓨팅에 적합한 LDPC 부호 복제 기법)

  • Kim, Se-Hoe;Lee, Won-Joo;Jeon, Chang-Ho
    • Journal of the Institute of Electronics Engineers of Korea CI
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    • v.49 no.2
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    • pp.134-142
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    • 2012
  • This paper analyze an LDPC code replication method suitable for cloud computing. First, we determine the number of blocks suitable for cloud computing through analysis of the performance for the file availability and storage overhead. Also we determine the type of LDPC code appropriate for cloud computing through the performance for three types of LDPC codes. Finally we present the graph random generation method and the comparing method of each generated LDPC code's performance by the iterative decoding process. By the simulation, we confirmed the best graph's regularity is left-regular or least left-regular. Also, we confirmed the best graph's total number of edges are minimum value or near the minimum value.