• 한국전자파학회논문지
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• 제15권5호
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• pp.517-524
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• 2004

광 위상 공액기(OPC: Optical Phase Conjugator)가 전체 전송 거리의 중간이 아닌 곳에 위치한 8-채널 WDM 시스템에서 두 전송 구간의 총 분산량 변동에 따른 각 채널의 보상 특성을 NRZ 형식과 RZ 형식별로 살펴보았다. 신호파를 공액파로 만드는 OPC의 비선형 매질로는 광대역 특성을 나타낼 수 있는 HNL-DSF(Highly- Non-linear Dispersion Shifted Fiber)를 사용했다. 우선 OPC를 중심으로 두 전송 구간의 총 분산량이 서로 동일하지 않은 WDM 전송 시스템에서는 전송 파형 형식으로 NRZ보다 RZ를 사용한 경우가 안정된 품질 유지에 더욱 유리하다는 것을 확인하였다. 또한 NRZ 파형 전송의 경우 OPC를 중심으로 두 전송 구간의 총 분산량을 동일하게 설정하는 것보다 상대적으로 길이가 짧은 전송 구간의 총 분산량을 길이가 긴 전송 구간의 총 분산량에 비해 작게 설정하여야 양호한 보상이 이루어지는 것을 확인하였다.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 1997년도 춘계학술대회 논문집
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• pp.416-421
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• 1997

This study presents a way to construct 3D shape in STL format from 2D slice data. Nowadays ahape reconstruct has been done in many ares, the application of this method is important especially in Reverse Engineering which reconstructs original shape from cross-section data. Current RP (Rapid Prototyping) is used not only for the verification of a part designed but also for the production and tooling in more effective way. In RP technology, data should be prepared in STL format. In this paper, the way to make 3D shape data in STL format form 2D slice data is described which can be used to reconstruct an original shape in RP equipment.

• Wind and Structures
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• 제4권1호
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• pp.45-62
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• 2001

This paper is focused on the torsional effects that are induced on bridge piers by unbalanced wind buffeting on the deck during double cantilever erection stages. The case of decks with variable cross section is considered in particular as this characteristic is typical of most frame bridges that are built by the cantilever method. The procedure outlined in the paper is basically an application of the method that Dyrbye and Hansen (1996) have illustrated for decks with constant cross section. This format was chosen because it is suitable for design purposes and may easily be implemented in structural codes. As a complement, the correspondence with the format that is adopted in the Canadian code (NBCC 1990) for the gust factor is established, which might be useful to bridge designers used to the North-American approach to the gust effects on structures. Only alongwind turbulence and horizontal movements of the deck are considered. The combination of torsional and bending effects is also discussed and it is illustrated with an example of application.

• 방송공학회논문지
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• 제25권5호
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• pp.723-733
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• 2020

본 고에서는 현재 탐색단계의 표준화가 진행 중인 MPEG-I Immersive Audio 표준화 동향을 소개한다. 이 표준은 5G/6G와 같은 초연결 환경에서 킬러 어플리케이션으로 기대되는 가상현실(Virtual Reality; VR) 및 증강현실(Augmemted Reality; AR)에서, 이용자가 가상환경과 상호작용을 통해 6 자유도(Degrees of freedom; DoF)로 소리를 실감나게 느끼고 실제 환경에서 경험하는 것과 같은 공간음향 체험을 제공하는 것을 목표로 한다. 이를 위하여, MPEG Audio Working Group에서는 가상현실 및 증강현실에서 공간음향 체험을 위한 시스템 구조 및 요구사항을 정의하였다. 이를 기반으로 요구사항에 대한 제안 기술 선정을 위한 오디오 평가 플랫폼(Audio evaluation platform; AEP), 인코더 입력 포맷(Encoder input format; EIF) 및 평가 절차 등에 대한 논의를 진행하고 있으며, 본 고에서는 그 주요 내용을 요약 기술한다.

• Nuclear Engineering and Technology
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• 제38권8호
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• pp.803-808
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• 2006

The neutron induced nuclear cross section data for Ir-191 and Ir-193 were calculated and evaluated from unresolved resonance energy to 20MeV. The energy-dependent optical model potential parameters were determined based on the experimental data and applied up to 20MeV. A spherical optical model, a statistical model in an equilibrium energy region, and a multistep direct and multistep compound model in a pre-equilibrium energy region were used in the calculations. The direct capture model enhanced the fast neutron capture in the pre-equilibrium energy. The theoretically calculated cross sections were compared with the experimental data and the evaluated files. The calculations were found to be in good agreement with the experiment data. The evaluated cross section results were compiled with the ENDF-6 format. The fast energy results will be merged with the resonance parts to create a full evaluation library. The improvement of the neutron-induced cross section data will contribute to an increase in the efficiency of the production of Ir-192 as a radiation source.

• Nuclear Engineering and Technology
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• 제37권1호
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• pp.101-108
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• 2005

The neutron induced nuclear cross-section data for Pd-105, Ag-109, Xe-131, and Cs-133 were calculated and evaluated from an unresolved energy to 20 MeV. The energy dependent optical model potential parameters were extracted based on recent experimental data and applied up to 20 MeV. A spherical optical model and a statistical model for the equilibrium energy, and a multistep direct and a multistep compound model for the pre-equilibrium energy were used in the calculation. The direct capture model was recently introduced for fast neutron capture. The theoretically calculated cross-sections were compared with the experimental data and the evaluated files. The total and capture cross-sections calculated using the model were in good agreement with the reference experimental data. The evaluated cross-section results were compiled in ENDF-6 format and merged with the resonance component, already adopted in the ENDF/B-VI release 8. New data library files covering from thermal to 20 MeV were created. They are at the preliminary stage of an ENDF/B- VII release.

• 디지털콘텐츠학회 논문지
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• 제12권1호
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• pp.77-83
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• 2011

기존의 유선 환경기반의 GIS 솔루션으로 무선 환경에서 서비스를 하기에는 제한된 통신 속도, 처리속도, 화면 사이즈 등의 한계점이 존재한다. 본 논문에서는 GIS 개발자들에 의해 개척되고 있는 최신의 기술인 모바일 지도 서비스에서 공간 데이터의 효율적 사용을 위한 공간 객체 표현, 저장 및 전송을 위한 파일 포맷인 MVF를 개발하였다. 본 논문에서는 먼저 MVF의 문법을 정의하고, API를 통한 MVF 생성을 위해 헤드섹션 생성모듈과 메인섹션 생성모듈을 구현하였다. 특히, 모바일 지도 서비스를 위해 개발된 MVF는 네트워크의 트래픽을 감소하기 위한 공간 데이터의 크기와 이용 효율을 위한 한글 처리에 대해 고려하였다.

• Nuclear Engineering and Technology
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• 제50권3호
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• pp.340-355
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• 2018

The methods and performance of a fast reactor multigroup cross section (XS) generation code EXUS-F are described that is capable of directly processing Evaluated Nuclear Data File format nuclear data files. RECONR of NJOY is used to generate pointwise XS data, and Doppler broadening is incorporated by the Gauss-Hermite quadrature method. The self-shielding effect is incorporated in the ultrafine group XSs in the resolved and unresolved resonance ranges. Functions to generate scattering transfer matrices and fission spectrum matrices are realized. The extended transport approximation is used in zero-dimensional calculations, whereas the collision probability method and the method of characteristics are used for one-dimensional cylindrical geometry and two-dimensional hexagonal geometry problems, respectively. Verification calculations are performed first for various homogeneous mixtures and cylindrical problems. It is confirmed that the spectrum calculations and the corresponding multigroup XS generations are performed adequately in that the reactivity errors are less than 50 pcm with the McCARD Monte Carlo solutions. The nTRACER core calculations are performed with the EXUS-F-generated 47 group XSs for the two-dimensional Advanced Burner Reactor 1000 benchmark problem. The reactivity error of 160 pcm and the root mean square error of the pin powers of 0.7% indicate that EXUF-F generates properly the broad-group XSs.

• 한국정보처리학회논문지
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• 제7권2호
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• pp.321-327
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• 2000

지리 정보 시스템(GIS; Geographical Information System)은 하드웨어, 소프트웨어, 데이터, 사람, 그리고 메소드로 구성된다. 이중 데이터는 GIS 의 가장 중요한 요소 중 하나이다. 본 논문에서는 GIS 개발자들에 의해 개척되고 있는 최신의 기술인 인터넷 GIS에서 공간 데이터의 효율적 사용을 위한 공간 객체 표현, 저장 및 전송을 위한 파일 포맷인 HVF를 개발하였다. 본 논문에서는 먼저 HVF의 문법을 정의하고, API를 통한 HVF 생성을 위해 헤드섹션 생성모듈과 메인섹션 생성모듈을 구현하였다. 그리고 HVF를 여러 응용 분야에서 데이터의 공유가 가능한 자료 구조의 형태로 변환하기 위해 HVF를 위한 공간객체 변환기를 개발하였다. 이를 위해 변환기를 구성하는 3개의 단위 모듈인 파일 처리 모듈, HVF 수입 모듈, 그리고 HVF 수출 모듈들을 설계 및 구현하였다. 특히, 인터넷 GIS를 위해 개발된 HVF는 네트워크의 트래픽을 감소하기 위한 공간 데이터의 크기와 이용 효율을 위한 한글 처리에 대해 고려 하였다.

• Nuclear Engineering and Technology
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• 제56권4호
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• pp.1204-1212
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• 2024

To accurately calculate the heating distribution of the fast reactor, a neutron-photon library in MATXS format named Knight-B7.1-1968n × 94γ was processed based on the ENDF/B-VII.1 library for ultrafine groups. The neutron cross-section processing code MGGC2.0 was used to generate few-group neutron cross sections in ISOTXS format. Additionally, the self-developed photon cross-section processing code NGAMMA was utilized to generate photon libraries for neutron-photon coupled heating calculations, including photo-atom cross sections for the ISOTXS format, prompt photon production cross sections, and kinetic energy release in materials (KERMA) factors for neutrons and photons, and the self-shielding effect from the capture and fission cross sections of neutron to photon have been taken into account when the photon source generated by neutron is calculated. The interface code GSORCAL was developed to generate the photon source distribution and interface with the DIF3D code to calculate the neutron-photon coupling heating distribution of the fast reactor core. The neutron-photon coupled heating calculation route was verified using the ZPPR-9 benchmark and the RBEC-M benchmark, and the results of the coupled heating calculations were analyzed in comparison with those obtained from the Monte Carlo code MCNP. The calculations show that the library was accurately processed, and the results of the fast reactor neutron-photon coupled heating calculations agree well with those obtained from MCNP.