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Volumn 25, Issue 11, 2002, Pages 1095-1102

The influence of surface roughness on fluid flow through cracks

Author keywords

Flowrate calculations; Fluid friction; Laminar flow; Leak before break; Turbulent flow

Indexed keywords

COMPUTATIONAL FLUID DYNAMICS; CRACKS; FLOW OF FLUIDS; LEAKAGE (FLUID);

EID: 0036852671     PISSN: 8756758X     EISSN: None     Source Type: Journal    
DOI: 10.1046/j.1460-2695.2002.00595.x     Document Type: Article
Times cited : (16)

References (10)
  • 6
    • 0022441869 scopus 로고
    • The flow resistance of experimental models of naturally occurring cracks
    • Gardiner, G.C. and Tyrrell, R.J. (1968) The flow resistance of experimental models of naturally occurring cracks. Proc. Inst Mech Engrs., 200, No. C4.
    • (1968) Proc. Inst Mech Engrs. , vol.200 , Issue.C4
    • Gardiner, G.C.1    Tyrrell, R.J.2
  • 7
    • 29144514987 scopus 로고
    • Assessment of fluid friction factors for use in leak rate calculations
    • Lyon, France. Proceedings of the US Nuclear Regulatory Commission, Washington D.C. NUREG/CP-0155
    • Chivers, T.C. (1995) Assessment of Fluid Friction Factors for use in Leak Rate Calculations. In: Proceedings of the Seminar on Leak Before Break in Reactor Piping and Vessels. Lyon, France. Proceedings of the US Nuclear Regulatory Commission, Washington D.C. NUREG/CP-0155.
    • (1995) Proceedings of the Seminar on Leak Before Break in Reactor Piping and Vessels
    • Chivers, T.C.1
  • 9
    • 5844357079 scopus 로고
    • Determination of crack morphology parameters from service failures for leak rate analysis
    • Lyon, France. Proceedings of the US Nuclear Regulatory Commission, Washington D.C. NUREG/CP-0155
    • Wilkowski, G., Rahman, S., Ghadiali, N. and Paul, D. (1995) Determination of Crack Morphology Parameters from Service Failures for Leak Rate Analysis. In: Proceedings of the Seminar on Leak Before Break in Reactor Piping and Vessels. Lyon, France. Proceedings of the US Nuclear Regulatory Commission, Washington D.C. NUREG/CP-0155.
    • (1995) Proceedings of the Seminar on Leak Before Break in Reactor Piping and Vessels
    • Wilkowski, G.1    Rahman, S.2    Ghadiali, N.3    Paul, D.4


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.