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Volumn 235, Issue 2-4, 2005, Pages 421-443

Fluid mixing and flow distribution in the reactor circuit, measurement data base

Author keywords

[No Author keywords available]

Indexed keywords

FLOW DISTRIBUTION; FLUID MIXING; REACTOR CIRCUIT;

EID: 11344271766     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2004.08.045     Document Type: Conference Paper
Times cited : (63)

References (14)
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    • San Francisco, CA, 3-8 October
    • Kliem, S., Höhne, T., Rohde, U., Weiß, F.-P., 1999. Main steam line break analysis of a VVER-440 reactor using the coupled thermohydraulics system/3D-neutron kinetics code DYN3D/ATHLET in combination with the CFD Code CFX-4. In: Proceedings of the Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-9). San Francisco, CA, 3-8 October.
    • (1999) Proceedings of the Ninth International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-9)
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  • 5
    • 84860066493 scopus 로고    scopus 로고
    • Data sets of the 1/5-scale slug mixing experiments at ROCOM facility
    • FZ Rossendorf, Germany +CDROM
    • Kliem, S., Rohde, U., Höhne, T., 2003. Data sets of the 1/5-scale slug mixing experiments at ROCOM facility. EU/FP5 FLOMIX-R Report, FLOMIX-R-D05, FZ Rossendorf, Germany, 47 pp. (+CDROM).
    • (2003) EU/FP5 FLOMIX-R Report , vol.FLOMIX-R-D05
    • Kliem, S.1    Rohde, U.2    Höhne, T.3
  • 6
    • 2342635847 scopus 로고    scopus 로고
    • Core response of a PWR to a slug of under-borated water
    • S. Kliem, U. Rohde, and F.-P. Weiß Core response of a PWR to a slug of under-borated water Nucl. Eng. Des. 230 2004 121 132
    • (2004) Nucl. Eng. Des. , vol.230 , pp. 121-132
    • Kliem, S.1    Rohde, U.2    Weiß, F.-P.3
  • 9
    • 0037559501 scopus 로고    scopus 로고
    • Coolant mixing in a pressurised water reactor: Deboration transients, steam-line breaks, and emergency core cooling injection
    • H.-M. Prasser, G. Grunwald, T. Höhne, S. Kliem, U. Rohde, and F.-P. Weiss Coolant mixing in a pressurised water reactor: deboration transients, steam-line breaks, and emergency core cooling injection Nucl. Technol. 143 2003 37 56
    • (2003) Nucl. Technol. , vol.143 , pp. 37-56
    • Prasser, H.-M.1    Grunwald, G.2    Höhne, T.3    Kliem, S.4    Rohde, U.5    Weiss, F.-P.6
  • 10
    • 0032100908 scopus 로고    scopus 로고
    • A new electrode-mesh tomograph for gas liquid flows
    • H.-M. Prasser, A. Böttger, and J. Zschau A new electrode-mesh tomograph for gas liquid flows Flow Meas. Instrum. 9 1998 111 119
    • (1998) Flow Meas. Instrum. , vol.9 , pp. 111-119
    • Prasser, H.-M.1    Böttger, A.2    Zschau, J.3
  • 11
    • 0031187588 scopus 로고    scopus 로고
    • Analysis of a boron dilution accident for WWER-440 combining the use of the codes DYN3D and SiTAP
    • U. Rohde, I. Elkin, and V. Kalinenko Analysis of a boron dilution accident for WWER-440 combining the use of the codes DYN3D and SiTAP Nucl. Eng. Des. 170 1997 95 99
    • (1997) Nucl. Eng. Des. , vol.170 , pp. 95-99
    • Rohde, U.1    Elkin, I.2    Kalinenko, V.3
  • 12
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    • Coolant temperature distribution at VVER-440 core inlet
    • C.A. Tsimbalov, and A.V. Kraiko Coolant temperature distribution at VVER-440 core inlet At. Energy 52 5 1982 304 308 (English translation, original in Russian)
    • (1982) At. Energy , vol.52 , Issue.5 , pp. 304-308
    • Tsimbalov, C.A.1    Kraiko, A.V.2
  • 13
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    • Thermal-hydraulics of the Loviisa reactor pressure vessel overcooling transients
    • Tuomisto, H., 1987. Thermal-hydraulics of the Loviisa reactor pressure vessel overcooling transients. Imatran Voima Oy, Research Report IVO-A-01/87.
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    • Tuomisto, H.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.