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Volumn 192, Issue 1, 1999, Pages 13-30

Prediction of air and steam leak rate through cracked reinforced concrete panels

Author keywords

[No Author keywords available]

Indexed keywords

AIR; CRACKS; LEAKAGE (FLUID); NUCLEAR REACTORS; NUMERICAL METHODS; REINFORCED CONCRETE; STEAM;

EID: 0033308759     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(99)00080-1     Document Type: Article
Times cited : (17)

References (19)
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  • 5
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    • DIANA TNO Building and Construction Research, Delft, The Netherlands
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    • (1996) DIANA User's Manual, Version 6.2.
  • 7
    • 85031591103 scopus 로고    scopus 로고
    • A Mock-up near Civaux nuclear power plant for containment evaluation under severe accidents - The MAEVA project
    • Lyon (13-18 August, 1997)
    • Granger, L., et al., 1997. A Mock-up near Civaux nuclear power plant for containment evaluation under severe accidents - The MAEVA project. Proc. SMIRT-97, Lyon (13-18 August, 1997).
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    • Granger, L.1
  • 8
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    • (1995) Nucl. Eng. Des. , vol.156 , pp. 167-172
    • Greiner, U.1    Ramm, W.2
  • 10
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    • Mass transfer of gas, water and water vapour trough concrete for reactor buildings
    • Mills, R.H., 1992. Mass transfer of gas, water and water vapour trough concrete for reactor buildings. Proc. 2nd Conf. on Containment of Nuclear Reactor.
    • (1992) Proc. 2nd Conf. on Containment of Nuclear Reactor
    • Mills, R.H.1
  • 13
    • 0343285584 scopus 로고
    • Experimental study of leakage through residual shear cracks on r/c walls
    • Session Q
    • Nagano, T., Kowada, A., Matumura, T., Inada, Y., Yajima, K., 1989. Experimental study of leakage through residual shear cracks on r/c walls. Proc. SMIRT-10, Session Q, pp. 139-144.
    • (1989) Proc. SMIRT-10 , pp. 139-144
    • Nagano, T.1    Kowada, A.2    Matumura, T.3    Inada, Y.4    Yajima, K.5
  • 14
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* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.