• Title/Summary/Keyword: Power/Signal Integrity

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A Study on the Radiated Emission from the DC Power-Bus for the PCB (PCB DC Power-Bus로부터의 전파 방사에 관한 연구)

  • Kahng, Sung-Tek
    • The Journal of Korean Institute of Electromagnetic Engineering and Science
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    • v.17 no.2 s.105
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    • pp.148-151
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    • 2006
  • The DC power-bus' resonance is frequently attributed to EMI sources in the PCBs. Subsequently, it will ruin the digital signal integrity within one system or between adjacent systems in the form of conducted or radiated emission. Hence, since it is of importance to examine the PCB's emission, this paper sheds a light on the radiated emission from the power-bus with regards to its resonance modes. A full-wave analysis method is used to calculate the impedance and radiated electric fields and is validated by physics and an EM analysis tool.

A 1.8V 2-Gb/s SLVS Transmitter with 4-lane (4-lane을 가지는 1.8V 2-Gb/s SLVS 송신단)

  • Baek, Seung-Wuk;Jang, Young-Chan
    • Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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    • 2013.10a
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    • pp.357-360
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    • 2013
  • A 1.8V 2-Gb/s scalable low voltage signaling (SLVS) transmitter (TX) is designed for mobile applications requiring high speed and low power consumption. It consists of 4-lane TX for data transmission, 1-lane TX for a source synchronous clocking, and a 8-phase clock generator. The proposed SLVS TX has the scaling voltage swing from 50 mV to 650 mV and supports a high speed (HS) mode and a low power (LP) mode. An output impedance calibration scheme for the SVLS TX is proposed to improve the signal integrity. The proposed SLVS TX is implemented by using a $0.18-{\mu}m$ 1-poly 6-metal CMOS with a 1.8V supply. The simulated data jitter of the implemented SLVS TX is about 8.04 ps at the data rate of 2-Gbps. The area and power consumption of the 1-lane of the proposed SLVS TX are $422{\times}474{\mu}m^2$ and 5.35 mW/Gb/s, respectively.

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Automatic Analysis of Gamma Ray Spectra for Surveillance of the Nuclear Fuel Integrity (핵연료 건전성 점검을 위한 감마선 스펙트럼의 자동 분석)

  • Cho, Joo-Hyun;Yu, Sung-Sik;Kim, Seong-Rae;Hah, Yung-Joon
    • Nuclear Engineering and Technology
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    • v.26 no.4
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    • pp.555-561
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    • 1994
  • The program of performing a fast and automatic analysis of gamma ray spectra obtained by a Multi-Channel Analyzer (MCA) is developed for the surveillance of the nuclear fuel integrity. The integrity of the nuclear fuel is confirmed by the measurement of the radiation level of the reactor coolant through the real time monitoring and the periodic sampling analysis. In Yonggwang nuclear power plane 3 and 4, the Process Radiation Monitoring System (PRMS), which is a real time monitoring system, provides a measure of the fuel integrity. Currently, its spectrometer channel can identify only one radionuclide at a time since the signal processing unit of the spectrometer channel is a Single Channel Analyzer (SCA). To improve the PRMS, it is necessary to substitute the MCA for the SCA The program is operated in a real time mode and an on-demand mode, and automatically performed for all procedures. The test results by using the National Bureau of Standards (NBS) mixed standard source are in good agreement with those from Canberra System 100 which is a commercial MCA Consequently, the developed program seems to be employed for automatic monitoring of gamma rays in nuclear power plants.

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A study on the radiated emission from the DC power-bus for the PCB (PCB DC power-bus로부터의 전파방사에 관한 연구)

  • Kahng, Sung-Tek
    • Proceedings of the Korea Electromagnetic Engineering Society Conference
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    • 2005.11a
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    • pp.149-152
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    • 2005
  • The DC power-bus' resonance is frequently attributed to EMI sources in the PCBs. Subsequently, it will ruin the digital signal integrity within one system or between adjacent systems in the form of conducted or radiated emission. Hence, since it is of importance to examine the PCB's emission, this paper sheds a light on the radiated emission from the power-bus with regards to its resonance modes. A full-wave analysis method is used to calculate the impedance and radiated electric fields and is validated by physics and an EM analysis tool.

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Design of Hardward Diagnostic System for Reactor Internal Structures Using Neutron Noise (중성자 신호이용 원자로 내부 구조물 감시시스템 하드웨어 설계)

  • Park, Jong-Beom;Park, Jin-Ho;Hwang, Choong-Hwan;Kim, Soo-Hong
    • Proceedings of the KIEE Conference
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    • 2001.07d
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    • pp.2166-2168
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    • 2001
  • Reactor Noise is defined as the fluctuations of measured instrumentation signals during full-power operation of reactor which have informations on reactor system dynamics such as neutron kinetics. The Reactor internal structures which consist of many complex components are subjected to flow-induced vibration due to high temperature and pressure in reactor coolant system. The above flow-induced vibration causes degradation of structural integrity of the reactor and may result in loosing mechanical binding component which might impact other equipment and component or cause flow blockage. It is important to analyze reactor noise signal for the early detection of potential problem or failure in order to diagnosis reactor integrity in the point of view of safety and plant economics. Detailed design of hardware diagnostic system reactor internal structures using neutron noise(RIDS).

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The Technology of Gigabit Interconnects for Communication Systems (통신시스템 기가비트 연결 설계기술)

  • 남상식;박종대
    • Proceedings of the IEEK Conference
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    • 1999.06a
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    • pp.149-153
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    • 1999
  • As VLSI technology advances rapidly, the operating frequency of digital systems becomes very fast. In such a high-speed system, there are many factors that threaten signal integrity. The noise sources in digital system include the noises in power supply, ground bounce and packaging media and distortions on single and multiple transmission lines. This paper will present a technology survey useful in the design of Gigabit interconnection systems. Some case studies have been constructed which show the lossy transmission line effect of skin effect. dielectric loss, with backplane connectors using the theoretical and practical conditions.

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Design Issues of Digital Display Interface

  • Jeong, Deog-Kyoon;Oh, Do-Hwan
    • 한국정보디스플레이학회:학술대회논문집
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    • 2007.08a
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    • pp.993-996
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    • 2007
  • Depending on applications where transmission bandwidth, wire distance, power consumption and EMI environments vary, design trade-offs must be made to optimize the display interface. After introducing the digital display interface architecture, topics such as cost, EMI, signal integrity, scalability and content protection are discussed with available techniques. Implementation issues are discussed regarding their cost and design complexity. Existing standards are reviewed and comparison on their strengths and shortcomings are discussed.

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Characteristics of Eddy Current Signals of Axial Notches in Steam Generator U-bend Tubes using Rotating Pancake Coils (회전코일 와전류신호를 이용한 증기발생기 곡관형 튜브의 축방향노치 신호의 특성)

  • Kim, Chang-Soo;Moon, Yong-Sig
    • Transactions of the Korean Society of Pressure Vessels and Piping
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    • v.8 no.3
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    • pp.7-12
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    • 2012
  • Steam generator tubes are critical boundary of the primary and secondary side in nuclear power plants. Eddy current testing is commonly used as the method of non-destructive testing for the safety and integrity of steam generator tubes in the nuclear power plants. Changes in the geometric shape act as a stress concentration factor likely to cause a defect during the steam generator operation. The mixed-signals with the geometric shape are distorted and attributes that are difficult to detect signals. An example is bending stress due to compression process at a U-bend occurring in the intrados region which has a small radius of curvature. The resulting change in the geometric shape may lead to a dent like occurrences. The dent can cause stress concentration and generates stress corrosion cracks. In this study, the steam generator tubes of nuclear power plant were selected to study for analysis of mixed-signal containing dent and stress corrosion cracks.

A Study on Quantitative Flaw Evaluation of Nuclear Power Plant Steam Generator Tube by Ultrasonic Testing (초음파를 이용한 원자력발전소 증기발생기 전열관의 정략적 결함 평가에 관한 연구)

  • Yoon, Byung-Sik;Kim, Yong-Sik;Lee, Hee-Jong;Lee, Yong-Ho
    • Journal of the Korean Society for Nondestructive Testing
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    • v.26 no.1
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    • pp.12-17
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    • 2006
  • A steam generator of nuclear power plant has thousands of thin tubes. These tubes play an important role in maintaining the pressure boundary between the primary and secondary side of nuclear power plant. The steam generator tube is easy to be damaged because of the severe operating conditions such as the high temperature and pressure. Therefore, tremendous efforts are made to assess the structural integrity of the steam generator tubes. The eddy current test is the most popular non-destructive test to assess the integrity of the tubes. However, the eddy current test has the limitation to size the flaw accurately because the eddy current signal behavior depends on the total volume of flaw. This paper shows the possibility that the ultrasonic test method can be applied to detect the flaws in the steam generator tubes and to measure them quantitatively. From the test results, it is expected that if the ultrasonic test is put to practical use in the steam generator tube inspection, the inspection results will be improved.

Eddy Current Bobbin Probe Design for Steam Generator Tubes in NPPs (원전 증기발생기 전열관 와전류검사 보빈탐촉자 설계)

  • Nam, Min-Woo;Lee, Hee-Jong;Jee, Dong-Hyun;Jung, Jee-Hong;Kim, Cheol-Gi
    • Journal of the Korean Society for Nondestructive Testing
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    • v.27 no.2
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    • pp.89-96
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    • 2007
  • The bobbin probe examination is basic and the important method among other ECT techniques for the steam generator tube integrity assesment that is practiced during each plant outage. The bobbin probe is one of the essential components which consist of the whole ECT examination system, and provides us a decisive data for the evaluation of tube integrity in compliance with acceptance criteria described in specific procedures. The selection of examination probe is especially important because the quality of acquired ECT data is determined by the probe design characteristics, such as geometry and operation frequency, and has enormous effects on examination results. In this study, An optimal differential bobbin probe is designed for the steam generator tube inspection in nuclear power plants(NPPs). Based on the test results for electrical and ECT signal characteristics, the prototype bobbin probe satisfies all the criteria.