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      KCI등재

      전산해석을 활용한 원전용 오리피스 플레이트 내의 고압유동 특성 연구

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      https://www.riss.kr/link?id=A103297411

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      다국어 초록 (Multilingual Abstract)

      The flow measuring system with orifice plate used in nuclear power plant must be qualified but the limitation of the test facility leads to use the numerical analysis instead of the calibration experiment of orifice plate with high pressure flow. The ...

      The flow measuring system with orifice plate used in nuclear power plant must be qualified but the limitation of the test facility leads to use the numerical analysis instead of the calibration experiment of orifice plate with high pressure flow. The discharge coefficient is calculated with the pressure drop and mass flow rate obtained from numerical analysis. And the discharge coefficient is compared to the calculation result of ISO 5167. Consequently, it is found that the numerical analysis is possibly used to justify the relation of differential pressure to the flow rate, which was obtained from calibration experiment. From the justification of orifice plate, the discharge coefficient from numerical analysis can be used in the differential pressure transducer of orifice plate and flow computer with which the flow value is modified in considering the difference of real condition to base pressure and temperature where the relation of flow and differential pressure was calibrated.

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      참고문헌 (Reference)

      1 김홍민, "배관구조에 따른 속도분포 변형과 선회가 오리피스 유량계의 압력차에 미치는 영향에 대한 수치적 연구" 대한기계학회 27 (27): 1450-1456, 2003

      2 "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants(The American Society of Mechanical Engineers, USA)"

      3 "Pressure Relief Devise Performance Test (The American National Standard, USA)"

      4 "Measurement of Fluid Flow by Means of Pressure Differential Devices Inserted in Circular Cross-section Conduits Running Full - Part 1: General Principles and Requirements (International Organization for Standardization, USA)"

      5 Kim, M.S., "Instrument Technology" Korea Shipbuilding Monthly Magazine 116-119, 2007

      6 "IEEE Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations"

      7 "IEEE Standard for Qualifying Calss 1E Equipment for Nuclear Power Generating Stations"

      8 "IEEE Standard for Qualification of Actuators for Power-Operated Valve Assemblies With Safety-Related Functions for Nuclear Power Plants"

      9 Shin, B.S, "Distortion of Flow Measurement by Various Inlet Velocity Profile of Orfice Flowmeter" 590-600, 2011

      10 Driskell, L., "Control-Valve Selection And Sizing" Instrument Society of America 113-131, 1983

      1 김홍민, "배관구조에 따른 속도분포 변형과 선회가 오리피스 유량계의 압력차에 미치는 영향에 대한 수치적 연구" 대한기계학회 27 (27): 1450-1456, 2003

      2 "Qualification of Active Mechanical Equipment Used in Nuclear Power Plants(The American Society of Mechanical Engineers, USA)"

      3 "Pressure Relief Devise Performance Test (The American National Standard, USA)"

      4 "Measurement of Fluid Flow by Means of Pressure Differential Devices Inserted in Circular Cross-section Conduits Running Full - Part 1: General Principles and Requirements (International Organization for Standardization, USA)"

      5 Kim, M.S., "Instrument Technology" Korea Shipbuilding Monthly Magazine 116-119, 2007

      6 "IEEE Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations"

      7 "IEEE Standard for Qualifying Calss 1E Equipment for Nuclear Power Generating Stations"

      8 "IEEE Standard for Qualification of Actuators for Power-Operated Valve Assemblies With Safety-Related Functions for Nuclear Power Plants"

      9 Shin, B.S, "Distortion of Flow Measurement by Various Inlet Velocity Profile of Orfice Flowmeter" 590-600, 2011

      10 Driskell, L., "Control-Valve Selection And Sizing" Instrument Society of America 113-131, 1983

      11 Kim, H.M, "Computational Flow Analysis According to Orifice Position in Feeding Line of LRE" 451-455, 2010

      12 Choi, W, "A Study on Flow Characteristics of Different Pulverized Coal Tube Orifice" 3106-3110, 2014

      13 Kim, D.-S, "A Study of Orifice Flowmeter with Low Losses" 55-60, 2007

      14 Kang, H.S, "A Numerical Study on the Optimum Size for the Orifice Located on the Steam Generator Cassette of Integral Reactor" 75-81, 1998

      15 Kim, J.H, "A Numerical Study of High Pressure Flow Characteristics in Nuclear Orifice" 44-45, 2017

      16 Lee, J.-I, "A Numerial Study on Flow Characteristics Through Orifice Flowmeter Depending on Upstream Straight Length" 2556-2560, 2016

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      학술지 이력

      학술지 이력
      연월일 이력구분 이력상세 등재구분
      2027 평가예정 재인증평가 신청대상 (재인증)
      2021-01-01 평가 등재학술지 유지 (재인증) KCI등재
      2018-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2015-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2011-01-01 평가 등재 1차 FAIL (등재유지) KCI등재
      2009-01-01 평가 등재학술지 유지 (등재유지) KCI등재
      2006-01-01 평가 등재학술지 선정 (등재후보2차) KCI등재
      2005-06-16 학술지명변경 외국어명 : Jpurnal of Computatuonal Fluids Engineering -> Korean Society of Computatuonal Fluids Engineering KCI등재후보
      2005-01-01 평가 등재후보 1차 PASS (등재후보1차) KCI등재후보
      2004-01-01 평가 등재후보 1차 FAIL (등재후보1차) KCI등재후보
      2002-07-01 평가 등재후보학술지 선정 (신규평가) KCI등재후보
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      학술지 인용정보

      학술지 인용정보
      기준연도 WOS-KCI 통합IF(2년) KCIF(2년) KCIF(3년)
      2016 0.2 0.2 0.19
      KCIF(4년) KCIF(5년) 중심성지수(3년) 즉시성지수
      0.16 0.15 0.405 0.05
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