• Title/Summary/Keyword: Secondary Code

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Efficient Usage of Secondary Scramble Code via Optical Repeater in W-CDMA System (W-CDMA 시스템에서 광중계기를 이용한 secondary-스크램블 코드의 효율적 활용방안에 대한 연구)

  • Jeon, Eun-Sung;Park, Jun-Hyo;Yang, Jang-Hoon;Kim, Dong-Ku
    • The Journal of Korean Institute of Communications and Information Sciences
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    • v.34 no.8C
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    • pp.731-741
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    • 2009
  • Optical repeater is often installed at the isolated area. Spatial separation makes it possible to reduce the inter-code interference when secondary scrambling codes are used for traffic connected through repeater. In this paper, we propose five secondary scrambling code usage scenarios with the aids of optical repeater to maximize the user capacity. In order to evaluate the performance, dynamic system level simulation is performed. We also propose a base station-repeater switching where each active users can change access points by comparing the channel condition from base station and repeater thorough secondary common pilot channel (S-CPICH) signal to noise-interference ratio (SINR). Moreover, primary-secondary scramble code replacing scheme is proposed which replaces secondary scramble code with primary scramble code when a call using primary scramble code is ended and its corresponding OVSF code is available to users using the secondary scramble code

Receiver Design for Satellite Navigation Signals using the Tiered Differential Polyphase Code

  • Jo, Gwang Hee;Noh, Jae Hee;Lim, Deok Won;Son, Seok Bo;Hwang, Dong-Hwan;Lee, Sang Jeong
    • Journal of Positioning, Navigation, and Timing
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    • v.10 no.4
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    • pp.307-313
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    • 2021
  • Modernized GNSS signal structures tend to use tiered codes, and all GNSSs use binary codes as secondary codes. However, recently, signals using polyphase codes such as Zadoff-Chu sequence have been proposed, and are expected to be utilized in GNSS. For example, there is Tiered Differential Polyphase Code (TDPC) using polyphase code as secondary code. In TDPC, the phase of secondary code changes every one period of the primary code and a time-variant error is added to the carrier tracking error, so carrier tracking ambiguity exists until the secondary code phase is found. Since the carrier tracking ambiguity cannot be solved using the general GNSS receiver architecture, a new receiver architecture is required. Therefore, in this paper, we describe the carrier tracking ambiguity and its cause in signal tracking, and propose a receiver structure that can solve it. In order to prove the proposed receiver structure, we provide three signal tracking results. The first is the differential decoding result (secondary code sync) using the general GNSS receiver structure and the proposed receiver structure. The second is the IQ diagram before and after multiplying the secondary code demodulation when carrier tracking ambiguity is solved using the proposed receiver structure. The third is the carrier tracking result of the legacy GPS (L1 C/A) signal and the signal using TDPC.

Secondary Code Determination and Signal Processing Results of GIOVE-B E5a (GIOVE-B 위성 E5a Secondary Code 결정 및 신호처리 결과)

  • Joo, In-One;Shin, Chun-Sik;Lee, Sang-Uk;Kim, Jae-Hoon
    • Journal of the Korean Society for Aviation and Aeronautics
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    • v.16 no.4
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    • pp.12-19
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    • 2008
  • GIOVE-B is the second experimental Galileo satellite for the Galileo In-Orbit Validation, which was launched by a Soyuz/Fregat rocket departing from the Baikonur cosmodrome in Kazakhstan on 27 April and now operated successfully. This paper presents the results obtained from processing of the E5a signal transmitted from the GIOVE-B. The acquisition and tracking of the data and pilot channels are performed by the E5a software receiver implemented by ETRI. Moreover, the paper suggests the GIOVE-B E5a-I/E5a-Q secondary code, which is determined by analyzing the correlation output of the primary correlator using the primary code.

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ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions

  • Takeda, Takeshi
    • Nuclear Engineering and Technology
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    • v.50 no.6
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    • pp.981-988
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    • 2018
  • An experiment was performed for the OECD/NEA ROSA-2 Project with the large-scale test facility (LSTF), which simulated a steam generator tube rupture (SGTR) accident due to a double-ended guillotine break of one of steam generator (SG) U-tubes with operator recovery actions in a pressurized water reactor. The relief valve of broken SG opened three times after the start of intact SG secondary-side depressurization as the recovery action. Multi-dimensional phenomena specific to the SGTR accident appeared such as significant thermal stratification in a cold leg in broken loop especially during the operation of high-pressure injection (HPI) system. The RELAP5/MOD3.3 code overpredicted the broken SG secondary-side pressure after the start of the intact SG secondary-side depressurization, and failed to calculate the cold leg fluid temperature in broken loop. The combination of the number of the ruptured SG tubes and the HPI system operation difference was found to significantly affect the primary and SG secondary-side pressures through sensitivity analyses with the RELAP5 code.

J-Integral Estimate for Circumferential Cracked Pipes Under Primary and Secondary Stress in R6, RCC-MR A16 (원주방향 균열 배관에 대한 R6, RCC-MR A16 코드에 의한 1,2 차 복합 하중하에서 J-적분 비교)

  • Nam, Hyun Suk;Oh, Chang Young;Kim, Yun Jae
    • Transactions of the Korean Society of Mechanical Engineers A
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    • v.37 no.5
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    • pp.631-640
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    • 2013
  • This paper provides a comparison of the J-integral estimation method under combined primary and secondary stress in the R6, RCC-MR A16 code. The comparisons of each code are based on finite element analysis using ABAQUS with regard to the crack shape, crack depth, and magnitude of secondary load. The estimate of the R6 code is conservative near $L_r=1$, and that of the RCC-MR A16 code is conservative near $L_r=0$. As a result, this paper proposes a modified method of J-integral estimation in the R6, RCC_MR A16 code. The J-integral using the modified method corresponds to the finite element analysis result.

Development of Electron Beam Monte Carlo Simulation and Analysis of SEM Imaging Characteristics (전자빔 몬테 카를로 시물레이션 프로그램 개발 및 전자현미경 이미징 특성 분석)

  • Kim, Heung-Bae
    • Journal of the Korean Society for Precision Engineering
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    • v.29 no.5
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    • pp.554-562
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    • 2012
  • Processing of Scanning electron microscope imaging has been analyzed in both secondary electron (SE) imaging and backscattered electron (BSE) image. Because of unique characteristics of both secondary electron and backscattered electron image, mechanism of imaging process and image quality are quite different each other. For the sake of characterize imaging process, Monte Carlo simulation code have been developed. It simulates electron penetration and depth profile in certain material. In addition, secondary electron and backscattered electron generation process as well as their spatial distribution and energy characteristics can be simulated. Geometries that has fundamental feature have been imaged using the developed Monte Carlo code. Two, SE and BSE images generation process will be discussed. BSE imaging process can be readily used to discriminate in both material and geometry by simply changing position and direction of BSE detector. The developed MC code could be useful to design BSE detector and their position. Furthermore, surface reconstruction technique is possibly developed at the further research efforts. Basics of Monte Carlo simulation method will be discussed as well as characteristics of SE and BSE images.

Wall Thinning Analyses for Secondary Side Piping of Domestic NPPs Using CHECWORKS Code (CHECWORKS 코드를 이용한 국내 원전 2차계통 배관감육 해석)

  • Hwang, K.M.;Jin, T.E.;Lee, S.H.;Kim, W.S.
    • Proceedings of the KSME Conference
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    • 2001.06d
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    • pp.807-812
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    • 2001
  • This paper represents the wall thinning analysis results for secondary side piping of two types of domestic nuclear power plants based on the DB establishment and F AC analysis study for NPP secondary system piping. CHECWORKS code utilized in this study has been applied world widely to wall thinning analyses for secondary side piping and its reliability has also been proved. The predicted wear rates for several piping systems of a pressurized water reactor NPP are compared with those of a pressurized heavy water reactor NPP and with the measured wear rates. On the basis of comparison results of the predicted and measured wear rates, the analysis results can be effectively applied to the development of a standard thinned pipe management program targeted all domestic nuclear power plants.

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MIDLOOP Code Analysis of a ROSA-IV/LSTF Experiment for the Loss of Residual Heat Removal System Event During Mid- loop Operation

  • Han, Kee-Soo;Lee, Cheol-Sin;Park, Chul-Jin;Kim, Hee-Cheol
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05b
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    • pp.683-690
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    • 1996
  • The MIDLOOP code has been developed for the evaluation of RES pressurization transients initiated from a loss-of-Residual Heat Removal System (RHRS) during mid-loop operation after reactor shutdown. It provides a fast running and realistic tool for studying parametrically the response of important plant parameters such as pressure, temperature, and level to various plant combinations of the primary side vent, makeup, and leakage procedures and the steam generator (SG) conditions. The code consists of ten nodes representing the primary and secondary sides of a nuclear power plant and can analyze the effect of air on the primary system pressurization and primary to secondary heat transfer. The analysis results of the MIDLOOP code are in good agreement with the ROSA-IV/LSTF experiment without opening in the RCS.

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A Study on Prediction of Metal Loss by Flow-Accelerated Corrosion in the CANDU NPP Secondary Piping Systems (침부식에 의한 CANDU형 원전 2차측 배관의 감육 예측에 관한 연구)

  • Shim, S.H.;Song, J.S.;Yoon, K.B.;Hwang, K.M.;Jin, T.E.;Lee, S.H.;Kim, W.S.
    • Proceedings of the KSME Conference
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    • 2001.06a
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    • pp.616-621
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    • 2001
  • Flow-accelerated corrosion(FAC) is a phenomenon that results in metal loss from piping, vessels, and equipment made of carbon steel. FAC occurs only under certain conditions of flow, chemistry, geometry, and material. Unfortunately, those conditions are in much of the high-energy piping in nuclear and fossil-fueled power plants. Also, for domestic NPP secondary pipings whose operating time become longer, more evidences of FAC have been reported. The authors are studying on FAC management using CHECWORKS, computer code developed by EPRI. This paper is on the prediction results of metal loss by FAC in the one of CANDU type NPP secondary piping systems.

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A Numerical Study on Flow-Accelerated Corrosion in Two Adjacent Elbows

  • Yun, Hun;Hwang, Kyeongmo;Moon, Seung-Jae
    • Corrosion Science and Technology
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    • v.15 no.1
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    • pp.6-12
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    • 2016
  • Flow-Accelerated Corrosion (FAC) is a well-known degradation mechanism that attacks the secondary piping in nuclear power plants. Since the Surry Unit 2 event in 1986, most nuclear power plants have implemented management programs to deal with damages in carbon and low-alloy steel piping. Despite the utmost efforts, damage induced by FAC still occurs in power plants around the world. In order to predict FAC wear, some computer programs were developed such as CHECWORKS, CICERO, and COMSY. Various data need to be input to these programs; the chemical composition of secondary piping, flow operating conditions and piping geometries. CHECWORKS, developed by the Electric Power Research Institute (EPRI), uses a geometry code to calculate geometry effects. Such a relatively simple geometry code is limited in acquiring the accuracy of FAC prediction. Recently, EPRI revisited the geometry code with the intention of updating it. In this study, numerical simulations were performed for two adjacent $90^{\circ}$ elbows and the results were analysed in terms of the proximity effect between the two adjacent elbows.