• 제목/요약/키워드: W code

검색결과 741건 처리시간 0.049초

코드그룹화에 의한 이중전송률 MC-CDMA 시스템의 성능분석 (Performance Analysis of Dualrate MC-CDMA Systems Based on Code Grouping)

  • 김남선
    • 한국산업정보학회논문지
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    • 제11권4호
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    • pp.112-120
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    • 2006
  • 다중 반송파 기술과 CDMA 기술이 결합된 MC-CDMA 시스템은 주파수 선택적 페이딩에 의한 신호감쇄를 완화시키면서 높은 전송률에 대한 요구를 만족시킬 수 있는 전송방식이다. 본 논문에서는 전송률이 서로 다른 다양한 서비스들을 지원하기 위한 새로운 비동기 MC-CDMA 시스템을 제안한다. 제안한 시스템에서는 W-CDMA 하향링크에 사용되는 채널화 코드인 orthogonal variable spreding factor(OVSF) 코드의 생성특성을 이용하여 발생된 OVSF 코드를 다중전송률 MC-CDMA의 확산부호로 사용한다. 사용자의 전송률에 따라 길이가 다른 OVSF 코드를 확산부호로 사용하며 OVSF 코드 트리에서 같은 가지에 속한 코드들을 사용하는 사용자들을 모아 그룹화를 한다. 제안된 다중 전송률 비동기 MC-CDMA 시스템을 위한 모델을 제시하길 이에 따른 시스템 성능분석을 행한다. 제안된 시스템과 직교부호를 확산부호로 사용하는 단일 전송률 MC-CDMA시스템의 성능과 비교 분석한다.

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W-CDMA 시스템의 SSDT 기지국 식별 부호 설계 (Design of SSDT Cell ID Codes for W-CDMA System)

  • 송영준
    • 대한전자공학회:학술대회논문집
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    • 대한전자공학회 2007년도 하계종합학술대회 논문집
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    • pp.69-70
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    • 2007
  • The code division multiple access (CDMA) system capacity is limited by the amount of interference of the system. To reduce the unnecessary interference, this paper proposes optimized cell identification (ID) codes for site selection diversity transmission (SSDT) power control in wideband code division multiple access system of third generation partnership project (3GPP). The proposed SSDT cell ID codes are designed to minimize the problem and to be easily decoded using simple fast Hadamard transformation (FHT) decoder.

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한글 코드에 무관한 한글 디코더의 설계에 관한 연구 (Design of Korean Decoder adaptable any korean code system)

  • 최익수;황희융
    • 대한전기학회:학술대회논문집
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    • 대한전기학회 1989년도 하계종합학술대회 논문집
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    • pp.465-467
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    • 1989
  • Many Korean graphic cards have been produced. But, due to the diversity of korean code system all korean graphic cards produced have been adapted in specific code system. Therfore, considering in KSC-5601-1987, the paper propose a Korean decoder independent of code system

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Three Dimensional Numerical Code for the Expanding Flat Universe

  • Min, Kyoung-W.
    • Journal of Astronomy and Space Sciences
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    • 제4권2호
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    • pp.101-106
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    • 1987
  • The current distribution of galaxies may contain clues to the condition of the universe when the galaxies condensed and to nature of the subsequent expansion of the universe. The development of this large scale structure can be studied by employing N-body computer simulations. The present paper describes the code developed for this purpose. The computer code calculates the motion of collisionless matter acting under the force of gravity in an expanding flat universe. The test run of the code shows the error less than 0.5% in 100 iterations.

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X-밴드 진행파관 증폭기 설계 및 제작 (Experimental investigation on an X-band Traveling-Wave-Tube Amplifier)

  • 나영호;손민호;주지한;김해진;최진주
    • 한국전자파학회:학술대회논문집
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    • 한국전자파학회 2002년도 종합학술발표회 논문집 Vol.12 No.1
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    • pp.384-388
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    • 2002
  • X-band(8-12㎓)에서 50W의 고출력을 내는 진행파관 증폭기를 설계하고 제작하여 측정하였다. 본 연구에서는 전자빔과 전자파가 상호작용을 일으키는 Interaction Circuit을 나선형구조로 구성하였고 저속파구조의 분산특성을 얻기 위해 Sheath helix 모델링 이론을 적용하였고 HFSS(High Frequency Structure Simulator) Code를 사용해 분산특성을 얻었으며 이를 바탕으로 제작하여 측정하였다. 또한 2D-MAGIC Code를 통해 전파 빔과 전자파와의 상호작용관계와 증폭기의 성능을 예측하였다. 시뮬레이션 결과 포화입력전력 100 mW를 넣었을 때 10㎓에서 43W의 출력전력과 26㏈의 이득을 얻을 수 있었으며 측정을 통해 입력전력 30mw일 때 8W의 출력, 24㏈의 이득을 얻을 수 있었다.

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Design and fabrication of beam dumps at the µSR facility of RAON for high-energy proton absorption

  • Jae Chang Kim;Jae Young Jeong;Kihong Pak;Yong Hyun Kim;Junesic Park;Ju Hahn Lee;Yong Kyun Kim
    • Nuclear Engineering and Technology
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    • 제55권10호
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    • pp.3692-3699
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    • 2023
  • The Rare isotope Accelerator complex for ON-line experiments in Korea houses several accelerator complexes. Among them, the µSR facility will be initially equipped with a 600 MeV and 100 kW proton beam to generate surface muons, and will be upgraded to 400 kW with the same energy. Accelerated proton beams lose approximately 20% of the power at the target, and the remaining power is concentrated in the beam direction. Therefore, to ensure safe operation of the facility, concentrated protons must be distributed and absorbed at the beam dump. Additionally, effective dose levels must be lower than the legal standard, and the beam dumps used at 100 kW should be reused at 400 kW to minimize the generation of radioactive waste. In this study, we introduce a tailored method for designing beam dumps based on the characteristics of the µSR facility. To optimize the geometry, the absorbed power and effective dose were calculated using the MCNP6 code. The temperature and stress were determined using the ANSYS Mechanical code. Thus, the beam dump design consists of six structures when operated at 100 kW, and a 400 kW beam dump consisting of 24 structures was developed by reusing the 100 kW beam dump.

PHASE-B PRE-SIMULATION USING BORON AND GADOLINIUM AS POISON IN THE MODERATOR SYSTEM FOR WOLSONG-1

  • Kim, Sung-Min;Kim, Hyeong-Taek;Donnelly, Jim;Marleau, Guy
    • Nuclear Engineering and Technology
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    • 제44권5호
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    • pp.551-560
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    • 2012
  • The Wolsong-1 (W-1) Phase-B pre-simulations were carried out in preparation for tests to be conducted for the restart of the reactor after a major refurbishment project that included replacement of the pressure tube. These pre-simulations for Wolsong-1 Phase-B differ from those in the past that were performed for the Wolsong-1,2,3,4 tests in that these tests use the WIMS/DRAGON/RFSP-IST code suite for verification of the tests and gadolinium instead of the traditional PPV/MULTICELL/RFSP code system and boron as poison in the moderator system. The use of gadolinium is deemed not to have domestically accumulated experience gained from the previous Phase-B tests. Thus, it is appropriate to conduct a study in order to gain a correct understanding and interpretation of potential differences in test results stemming from using gadolinium rather than boron. Although the calibration of the reactivity device will not be noticeably different using boron and gadolinium at a constant moderator temperature, the temperature dependency of the neutronic behavior due to the presence of gadolinium in the moderator system might be pronounced. The results of the pre-simulations using gadolinium revealed that the moderator temperature reactivity coefficients indeed showed significant differences in comparison with those with boron. In order to secure the validity of the analysis results, the newly acquired WIMS/DRAGON/RFSP-IST code suite was verified against the W-2,3,4 Phase-B test results. The results of the new code suite verifications revealed some overall improvements in accuracy; justification of the use of the code can be claimed for the validation of the W-1 Phase-B test results.

우리나라 건축물 설계 스펙트럼에 상응하는 지진규모와 진앙거리의 추정 (Estimation of Earthquake Magnitude-Distance Combination Corresponding to Design Spectrum in Korean Building Code 2016)

  • 정기현;이한선;황경란
    • 한국지진공학회논문집
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    • 제21권1호
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    • pp.31-39
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    • 2017
  • In this study, to estimate the combination of earthquake magnitude ($M_w$) and distance (R) corresponding to the design spectrum defined in Korean Building Code (KBC) 2016, the response spectra predicted from the attenuation relationships with the variation of $M_w$ (5.0~7.0) and R (10~30km) are compared with the design spectrum in KBC 2016. Four attenuation relationships, which were developed based on local site characteristics and seismological parameters in Southern Korea and Eastern North America (ENA), are used. As a result, the scenario ground motions represented by the combinations of $M_w$ and R corresponding to the design spectrum for Seoul defined in KBC 2016 are estimated as (1) when R =10 km, $M_w=6.2{\sim}6.7$; (2) when R = 15 km, $M_w=6.5{\sim}6.9$; and (3) when R = 20 km, $M_w=6.7{\sim}7.1$.

DEVELOPMENT AND VALIDATION OF A NUCLEAR FUEL CYCLE ANALYSIS TOOL: A FUTURE CODE

  • Kim, S.K.;Ko, W.I.;Lee, Yoon Hee
    • Nuclear Engineering and Technology
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    • 제45권5호
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    • pp.665-674
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    • 2013
  • This paper presents the development and validation methods of the FUTURE (FUel cycle analysis Tool for nUcleaR Energy) code, which was developed for a dynamic material flow evaluation and economic analysis of the nuclear fuel cycle. This code enables an evaluation of a nuclear material flow and its economy for diverse nuclear fuel cycles based on a predictable scenario. The most notable virtue of this FUTURE code, which was developed using C# and MICROSOFT SQL DBMS, is that a program user can design a nuclear fuel cycle process easily using a standard process on the canvas screen through a drag-and-drop method. From the user's point of view, this code is very easy to use thanks to its high flexibility. In addition, the new code also enables the maintenance of data integrity by constructing a database environment of the results of the nuclear fuel cycle analyses.