ISSN Online: 2377-424X
International Heat Transfer Conference 12
Nuclear Engineering
Tabla de Contenidos
Analysis of axisymmetric heat conduction pertaining to a new axial power monitor for nuclear reactors
6 pages
DOI: 10.1615/IHTC12.4230
Study of the effects of non-condensable in a passive condenser system for the advanced boiling water reactor
6 pages
DOI: 10.1615/IHTC12.4250
Interfacial Transport Phenomena and Stability in Liquid-Metal/Water
6 pages
DOI: 10.1615/IHTC12.4260
Fluiddynamics in a windowless symmetrical target for accelerator driven hybrid nuclear reactors
6 pages
DOI: 10.1615/IHTC12.4270
Numerical predictions of the critical heat flux for inverted geometries with different heated area size
6 pages
DOI: 10.1615/IHTC12.4280
The Steam Explosion Induced by the Molten Reactor Material-Water Interaction
6 pages
DOI: 10.1615/IHTC12.4290
Thermal Evaluations for an Experiment in the Advanced Test Reactor Irradiation Test Vehicle
6 pages
DOI: 10.1615/IHTC12.4300
Improvements in reactor code RELAP5/MOD2 to predict void distribution and flow instability for low-pressure subcooled boiling flows
6 pages
DOI: 10.1615/IHTC12.4310
Two-phase flow distribution in the outlets of a horizontal multi-branch header
6 pages
DOI: 10.1615/IHTC12.4320
Heat Removal Mechanism of Passive Containment Cooling System for ALWR
6 pages
DOI: 10.1615/IHTC12.4330
Uncertainty evaluation of simulation of E-108 test facility experiments
6 pages
DOI: 10.1615/IHTC12.4340
ACCIDENT LOCALIZATION SYSTEM RESPONSE IN THE CASE OF MAIN STEAM RELIEF VALVE OPENING
6 pages
DOI: 10.1615/IHTC12.4350
Implementation of preventive measures against local flow degradation in the primary circuit of RBMK-1500
6 pages
DOI: 10.1615/IHTC12.4360