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ISSN Online: 2377-424X

International Heat Transfer Conference 12
August, 18-23, 2002, Grenoble, France

Nuclear Engineering

内容

Analysis of axisymmetric heat conduction pertaining to a new axial power monitor for nuclear reactors Niranjan K. Talukder , Negash G. Medhin 6 pages DOI: 10.1615/IHTC12.4230
Mass discharge through branches in horizontal two-phase flows Francesco Castiglia, Mariarosa Giardina 6 pages DOI: 10.1615/IHTC12.4240
Study of the effects of non-condensable in a passive condenser system for the advanced boiling water reactor Shripad Revankar 6 pages DOI: 10.1615/IHTC12.4250
Interfacial Transport Phenomena and Stability in Liquid-Metal/Water Sherif Abdulla, Xin Liu, Mark H. Anderson, Riccardo Bonazza, Michael L. Corradini, Day Cho, Dick Page 6 pages DOI: 10.1615/IHTC12.4260
Fluiddynamics in a windowless symmetrical target for accelerator driven hybrid nuclear reactors Mario De Salve, Mario Malandrone, Bruno Panella 6 pages DOI: 10.1615/IHTC12.4270
Numerical predictions of the critical heat flux for inverted geometries with different heated area size Zoran V. Stosic, Vladimir D. Stevanovic 6 pages DOI: 10.1615/IHTC12.4280
The Steam Explosion Induced by the Molten Reactor Material-Water Interaction J. H. Song, I. K. Park, Yongseung Shin, J. H. Kim, S.W. Hong, B. T. Min, Y. J. Chang, H. D. Kim 6 pages DOI: 10.1615/IHTC12.4290
Thermal Evaluations for an Experiment in the Advanced Test Reactor Irradiation Test Vehicle R. G. Ambrosek, M. P. Metcalfe, J. W. Sterbentz 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 Guan Heng Yeoh, Jiyuan Tu 6 pages DOI: 10.1615/IHTC12.4310
Two-phase flow distribution in the outlets of a horizontal multi-branch header Z. Teclemariam, Hassan M. Soliman, G. E. Sims, J.E. Kowalski 6 pages DOI: 10.1615/IHTC12.4320
Heat Removal Mechanism of Passive Containment Cooling System for ALWR Seiichi Yokobori, Toshimi Tobimatsu, Tomohisa Kurita, Makoto Akinaga, Kenji Arai, Hirohide Oikawa 6 pages DOI: 10.1615/IHTC12.4330
Uncertainty evaluation of simulation of E-108 test facility experiments Rolandas Urbonas 6 pages DOI: 10.1615/IHTC12.4340
ACCIDENT LOCALIZATION SYSTEM RESPONSE IN THE CASE OF MAIN STEAM RELIEF VALVE OPENING Benediktas B. Cesna, Sigitas Rimkevicius 6 pages DOI: 10.1615/IHTC12.4350
Implementation of preventive measures against local flow degradation in the primary circuit of RBMK-1500 Eugenijus Uspuras, Algirdas Kaliatka 6 pages DOI: 10.1615/IHTC12.4360
Thermal-hydraulic analysis of loss of long-term core cooling accidents at RBMK-1500 Algirdas Kaliatka, Eugenijus Uspuras 6 pages DOI: 10.1615/IHTC12.4370
Convective processes in spent nuclear fuel canisters Glenn E. McCreery, Keith G. Condie, Randy C. Clarksean, Donald M. McEligot 6 pages DOI: 10.1615/IHTC12.4380