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Annals of the Assembly for International Heat Transfer Conference 13

 

ISBN 1-56700-225-0 / CD 1-56700-226-9

Volumes per year:

various

For Online Access

Year 2006

Volume - Nuclear

DOI: 10.1615/IHTC13.p7    


Table of Contents:

  • THERMAL HYDRAULIC ANALYSIS OF SPENT FUEL SUBASSEMBLY DURING TRANSPORTATION FROM FBTR TO REPROCESSING FACILITY
    D. Sujish, C. Meikandamurthy, T. R. Ellappan, M. Rajan, G. Vaidyanathan

    DOI: 10.1615/IHTC13.p7.10
    NCL-01 pages

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  • EXPERIMENTAL STUDY ON THE THERMAL HYDRAULIC PHENOMENA DURING OPERATIONAL TRANSIENTS OF THE INTEGRAL TYPE REACTOR
    M. K. Chung, K. Y. Choi, H. S. Park, S. J. Yi

    DOI: 10.1615/IHTC13.p7.20
    NCL-02 pages

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  • THERMAL STRATIFICATION IN NUCLEAR REACTOR PIPING SYSTEM
    H. C. Rezende, M. A. Navarro, A. A. C. dos Santos

    DOI: 10.1615/IHTC13.p7.30
    NCL-03 pages

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  • INFLUENCE OF TEMPERATURE ON A WHIRLPOOL FORMATION IN THE COOLING SYSTEM OF A NUCLEAR REACTOR
    Mark K. M. Ho, Y. A. Stepanyants, G. Y. Yeoh

    DOI: 10.1615/IHTC13.p7.40
    NCL-04 pages

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  • CFD ANALYSIS OF NUCLEAR REACTOR THERMAL-HYDRAULICS WITH EXPERIMENTAL VALIDATION OF REACTOR VESSEL HEAD COOL-DOWN UNDER NATURAL CIRCULATION CONDITIONS
    J. Katolicky, M. Blaha, Miroslav Jicha, J. Frelich

    DOI: 10.1615/IHTC13.p7.50
    NCL-05 pages

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  • HEAT TRANSFER TO WATER THROUGH THE CRITICAL POINT
    J. Licht, P. Allex, M. Anderson

    DOI: 10.1615/IHTC13.p7.60
    NCL-06 pages

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  • THE THERMAL-HYDRAULIC CALCULATION MODEL FOR GAS FLOW IN A FUEL ROD ASSEMBLY
    Benediktas B. Cesna

    DOI: 10.1615/IHTC13.p7.70
    NCL-07 pages

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  • MODELLING OF PROCESSES WITH DISBALANCE OF HEAT GENERATION AND HEAT SINK IN RBMK-1500 REACTOR
    Eugenijus Uspuras, Rolandas Urbonas, Algirdas Kaliatka

    DOI: 10.1615/IHTC13.p7.80
    NCL-08 pages

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  • SUBCOOLED BOILING PHENOMENA IN THE PRESSURIZED WATER REACTOR DOWNCOMER DURING THE REFLOOD PHASE OF LBLOCA
    D. J. Euh, B. J. Yun, Y. J. Youn, C.-H. Song

    DOI: 10.1615/IHTC13.p7.90
    NCL-09 pages

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  • TRANSIENT SIMULATION OF NUCLEAR REACTOR SAFETY BASED ON A NEW CHOKED FLOW MODEL
    M. S. Chung, J. W. Kim

    DOI: 10.1615/IHTC13.p7.100
    NCL-10 pages

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  • ASSESSMENT OF HEAT MASS TRANSFER ANALOGY IN CONDENSATION MODELS OF NUCLEAR SAFETY CODES
    Luis E. Herranz, J. Fontanet, M. Vela-Garcia

    DOI: 10.1615/IHTC13.p7.110
    NCL-11 pages

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  • NUCLEAR FUEL CELLS WITH VARIABLES SOURCES
    T. A. Alves, M. F. Pelegrini, R. A. V. Ramos, C. R. M. Maia

    DOI: 10.1615/IHTC13.p7.120
    NCL-12 pages

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