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Home Archives Thermal Letter Officers Future meetings Assembly for International Heat Transfer Conferences

ISBN : 0-89116-559-2

International Heat Transfer Conference 8
1986, 17-22 August, San Francisco, USA

Nuclear Reactor Heat Transfer

Table of Contents:

SUBCHANNEL MEASUREMENTS OF THE EQUILIBRIUM QUALITY AND MASS FLUX DISTRIBUTION IN A ROD BUNDLE Richard T. Lahey, Jr. pages 2399-2404 DOI: 10.1615/IHTC8.3210
THE EFFECT ON LOCAL HEAT TRANSFER OF BOWING OF PINS IN A CLUSTER F. P. Berger, A. Erfan, A. C. Rapier, A. Ziai pages 2405-2410 DOI: 10.1615/IHTC8.3220
MUNGOS - FULLY INTERACTIVE MODEL FOR SUBCHANNEL ANALYSIS Z. V. Stosic , J. R. Riznic pages 2411-2416 DOI: 10.1615/IHTC8.3230
EXPERIMENTAL STUDY OF NONEQUILI BR IUM POST-CHF HEAT TRANSFER IN ROD BUNDLES C. Unal, Kemal Tuzla, O. Badr, S. Neti, John C. Chen pages 2417-2422 DOI: 10.1615/IHTC8.3240
STUDIES ON DRYOUT AND POST-DRYOUT HEAT TRANSFER T. Siikonen, T. Vanttola pages 2423-2428 DOI: 10.1615/IHTC8.3250
CRITICAL HEAT FLUX IN FLOW TRANSIENTS Gian Piero Celata, Maurizio Cumo, Francesco D'Annibale , G. E. Farello, T. Setaro pages 2429-2435 DOI: 10.1615/IHTC8.3260
HEAT TRANSFER, CARRYOVER AND FALL BACK IN NUCLEAR STEAM GENERATORS DURING TRANSIENTS Lih-Yih Liao, Alex Parlos , Peter Griffith pages 2437-2442 DOI: 10.1615/IHTC8.3270
EFFECT OF DIAMETER AND GEOMETRY ON TWO-PHASE FLOW REGIMES AND CARRY-OVER IN A MODEL PWR HOT LEG A. Hashemi , Jong H. Kim, J. P. Sursock pages 2443-2451 DOI: 10.1615/IHTC8.3280
Transient Analysis of Nuclear U-tube Steam Generator Zeljko Bogdan, Naim Hamdia Afgan pages 2453-2458 DOI: 10.1615/IHTC8.3290
TRANSIENT VOID FRACTION PREDICTIONS AT ELEVATED PRESSURES IN ONCE-THROUGH INTEGRAL SYSTEM Yassin A. Hassan pages 2459-2466 DOI: 10.1615/IHTC8.3300
A MULTI-TUBE STEADY STATE MODEL OF STRAIGHT AND U-TUBE STEAM GENERATORS IN A FAST REACTOR T. Fallows pages 2467-2472 DOI: 10.1615/IHTC8.3310
TESTS ON AN ELECTRICALLY HEATED SODIUM HEAT PIPE FOR TEMPERATURE CONTROL OF IRRADIATION EXPERIMENTS IN THE UK PROTOTYPE FAST REACTOR J. C. Ralph , G. Chaffey pages 2473-2478 DOI: 10.1615/IHTC8.3320
FAST BREEDER POOL TYPE REACTOR RELATIONSHIP BETWEEN OPERATING CONDITIONS, THERMAL HYDRAULICS, THERMAL LOADS AND THERMOMECHANICAL BEHAVIOUR Jean Pierre Kung , Michel Nedelec pages 2479-2483 DOI: 10.1615/IHTC8.3330
THERMAL PERFORMANCE OF FRESH MIXED-OXIDE FUEL IN A FAST FLUX LMR J. L. Ethridge, R. B. Baker pages 2485-2490 DOI: 10.1615/IHTC8.3340
SCALED WATER EXPERIMENTS TO SIMULATE IN-VESSEL NATURAL CIRCULATION IN SODIUM COOLED REACTORS Sukhminder S. Grewal, R.W. McGriff, L.F. Peterson, E.L. Gluekler , P.M. Magee pages 2491-2496 DOI: 10.1615/IHTC8.3350
Transient Thermal Mixing In A Model PWR Downcomer And Attached Cold Leg With Simulated High Pressure Injection A. Hashemi , J. Goodman , J. P. Sursock pages 2497-2503 DOI: 10.1615/IHTC8.3360
THERMAL MIXING FLOW VISUALIZATION Paul H. Rothe , Javier A. Valenzuela , Bill K.-H. Sun pages 2505-2510 DOI: 10.1615/IHTC8.3370
STEAM GENERATOR FEEDLINE BREAK SIMULATION TESTS H. A. Khater , Charles Fraser Forrest , W. I. Midvidy, N.N. Wahba pages 2511-2516 DOI: 10.1615/IHTC8.3380
THE MODELLING OF VESSEL HEAT TRANSFER PHENOMENA IN PWR SEVERE ACCIDENT ANALYSIS J. N. Lillington , A. J. Lyons pages 2517-2522 DOI: 10.1615/IHTC8.3390
CORE THERMAL RESPONSE AND MASS DISTRIBUTION DURING VESSEL MASS DEPLETION ASSOCIATED WITH A SBLOCA G. G. Loomis pages 2523-2527 DOI: 10.1615/IHTC8.3400
A TWO-PHASE FLOW HEAT TRANSFER CORRELATION PACKAGE SUITABLE FOR A PRESSURIZED WATER REACTOR SAFETY CODE J. C. Micaelli, C. Renault pages 2529-2534 DOI: 10.1615/IHTC8.3410
THE HEAT TRANSFER RESISTANCE OF A DEPOSIT ON THE GAS SIDE OF THE BOILER TUBES AT HINKLEY POINT 'A' NUCLEAR POWER STATION AND ITS EFFECT ON STATION ELECTRICAL GENERATION R. J. Paynter , Ð’.J. Roberts pages 2535-2540 DOI: 10.1615/IHTC8.3420
COMPUTATIONS OF FLOW AND HEAT TRANSFER IN POWER PLANT CONDENSERS L.N. Carlucci pages 2541-2546 DOI: 10.1615/IHTC8.3430
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