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NTIS 바로가기한국전산유체공학회지 = Journal of computational fluids engineering, v.22 no.4 = no.79, 2017년, pp.74 - 80
김재형 (한국기계연구원 원자력기기검증센터) , 이상혁 (한국기계연구원 원자력기기검증센터) , 이정희 (한국해양과학기술원 부설 선박해양플랜트연구소 해양플랜트산업기술센터)
The flow measuring system with averaging pitot tube 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 with high pressure flow. The multiplication of flow coefficient and expansion factor is ...
ASME QME-1a-1998, Qualification of Active Mechanical Equipment Used in Nuclear Power Plants(The American Society of Mechanical Engineers, USA, 1998), pp.1-112.
ISO 5167-1, 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, 2003), pp.5-6.
IEEE Std. 383-1974, IEEE Standard for Type Test of Class 1E Electric Cables, Field Splices, and Connections for Nuclear Power Generating Stations, Nuclear Power Engineering Committee of the IEEE Power Engineering Society (Institute of Electrical and Electronics Engineers, USA, 1974), pp.7-15.
IEEE Std. 382-1996, IEEE Standard for Qualification of Actuators for Power-Operated Valve Assemblies With Safety-Related Functions for Nuclear Power Plants, Nuclear Power Engineering Committee of the IEEE Power Engineering Society (Institute of Electrical and Electronics Engineers, USA, 1996), pp.1-47.
IEEE Std. 323-1983, IEEE Standard for Qualifying Calss 1E Equipment for Nuclear Power Generating Stations, Nuclear Power Engineering Committee of the IEEE Power Engineering Society (Institute of Electrical and Electronics Engineers, USA, 1983), pp.1-17.
2003, Kim, H.-M., Kim, K.-Y. and Her, J.-Y., "Numerical Study on the Effects of Velocity Profile Distortion and Swirl on Pressure Difference of Orifice Flowmeter Due to Pipe Structure," KSME(Korean Society of Mechanical Engineers) Transactions, Vol.B27, No.10, pp.1450-1456.
2017, Kim, J.H. and Lee, J.H, "A Numerical Study of High Pressure Flow Characteristics in Nuclear Orifice," in KSCFE 2017 Spring Conference, Proceedings, Vol.1, pp.44-45.
ASME PTC 25, Pressure Relief Devise Performance Test( The American National Standard, USA, 2008), p.16.
Driskell, L., Control-Valve Selection And Sizing (Instrument Society of America, USA, 1983), pp.113-131.
Kim, M.S., Instrument Technology (Korea Shipbuilding Monthly Magazine, Korea, 2007), pp.116-119.
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