ISSN Online: 2377-424X
ISBN Print: 0-89116-559-2
International Heat Transfer Conference 8
Nuclear Reactor Heat Transfer
Tabla de Contenidos
SUBCHANNEL MEASUREMENTS OF THE EQUILIBRIUM QUALITY AND MASS FLUX DISTRIBUTION IN A ROD BUNDLE
pages 2399-2404
DOI: 10.1615/IHTC8.3210
THE EFFECT ON LOCAL HEAT TRANSFER OF BOWING OF PINS IN A CLUSTER
pages 2405-2410
DOI: 10.1615/IHTC8.3220
EXPERIMENTAL STUDY OF NONEQUILI BR IUM POST-CHF HEAT TRANSFER IN ROD BUNDLES
pages 2417-2422
DOI: 10.1615/IHTC8.3240
HEAT TRANSFER, CARRYOVER AND FALL BACK IN NUCLEAR STEAM GENERATORS DURING TRANSIENTS
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
pages 2443-2451
DOI: 10.1615/IHTC8.3280
TRANSIENT VOID FRACTION PREDICTIONS AT ELEVATED PRESSURES IN ONCE-THROUGH INTEGRAL SYSTEM
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
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
pages 2473-2478
DOI: 10.1615/IHTC8.3320
FAST BREEDER POOL TYPE REACTOR RELATIONSHIP BETWEEN OPERATING CONDITIONS, THERMAL HYDRAULICS, THERMAL LOADS AND THERMOMECHANICAL BEHAVIOUR
pages 2479-2483
DOI: 10.1615/IHTC8.3330
THERMAL PERFORMANCE OF FRESH MIXED-OXIDE FUEL IN A FAST FLUX LMR
pages 2485-2490
DOI: 10.1615/IHTC8.3340
SCALED WATER EXPERIMENTS TO SIMULATE IN-VESSEL NATURAL CIRCULATION IN SODIUM COOLED REACTORS
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
pages 2497-2503
DOI: 10.1615/IHTC8.3360
THE MODELLING OF VESSEL HEAT TRANSFER PHENOMENA IN PWR SEVERE ACCIDENT ANALYSIS
pages 2517-2522
DOI: 10.1615/IHTC8.3390
CORE THERMAL RESPONSE AND MASS DISTRIBUTION DURING VESSEL MASS DEPLETION ASSOCIATED WITH A SBLOCA
pages 2523-2527
DOI: 10.1615/IHTC8.3400
A TWO-PHASE FLOW HEAT TRANSFER CORRELATION PACKAGE SUITABLE FOR A PRESSURIZED WATER REACTOR SAFETY CODE
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
pages 2535-2540
DOI: 10.1615/IHTC8.3420
COMPUTATIONS OF FLOW AND HEAT TRANSFER IN POWER PLANT CONDENSERS
pages 2541-2546
DOI: 10.1615/IHTC8.3430