A Study on the Debris Dispersal Fraction from the Cavity with the Capture Volume During HPME (Englisch)
- Neue Suche nach: Hong, S.-W.
- Neue Suche nach: Kim, H.-D.
- Neue Suche nach: Hong, S.-W.
- Neue Suche nach: Kim, H.-D.
In:
Advanced reactors safety
;
937-944
;
1997
-
ISBN:
- Aufsatz (Konferenz) / Print
-
Titel:A Study on the Debris Dispersal Fraction from the Cavity with the Capture Volume During HPME
-
Beteiligte:Hong, S.-W. ( Autor:in ) / Kim, H.-D. ( Autor:in )
-
Kongress:International topical meeting; 2nd, Advanced reactors safety ; 1997 ; Orlando; FL
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Erschienen in:Advanced reactors safety ; 937-944
-
Verlag:
- Neue Suche nach: American Nuclear Society
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Erscheinungsort:La Grange Park, IL
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Erscheinungsdatum:01.01.1997
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Format / Umfang:8 pages
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Anmerkungen:Also known as ARS'97
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ISBN:
-
Medientyp:Aufsatz (Konferenz)
-
Format:Print
-
Sprache:Englisch
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Schlagwörter:
-
Datenquelle:
© Metadata Copyright the British Library Board and other contributors. All rights reserved.
Inhaltsverzeichnis Konferenzband
Die Inhaltsverzeichnisse werden automatisch erzeugt und basieren auf den im Index des TIB-Portals verfügbaren Einzelnachweisen der enthaltenen Beiträge. Die Anzeige der Inhaltsverzeichnisse kann daher unvollständig oder lückenhaft sein.
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AP-600-Safety Through SimplicityBruschi, H. J. et al. | 1997
- 9
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Advanced Reactor Development Programs in KoreaKim, S.-Y. et al. | 1997
- 14
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Light Water Reactor Safety Perspectives Derived from 25 Years R&D Experience at the Karlsruhe Research CenterHennies, H.-H. et al. | 1997
- 23
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Policy of EdF for the Future of Nuclear Power Generation Safety and EconomyRoche, B. et al. | 1997
- 29
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Adoption of Passive Features in Korean Nuclear SystemsChang Sun Kang et al. | 1997
- 39
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LMFBR Operation in the Nuclear Cycle Without Fuel ReprocessingToshinsky, G. I. et al. | 1997
- 45
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Safety of a Light Water Cooled Reactor Operating at Supercritical PressureOka, Y. / Koshizuka, S. / Lee, J. H. / Okano, Y. et al. | 1997
- 53
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Core and Plant Design of the Power Reactor Cooled and Moderated by Supercritical Light WaterDobashi, K. / Oka, Y. / Koshizuka, S. et al. | 1997
- 61
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- 74
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- 81
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Crust Formation and Its Effect on Heat Transfer in the Molten Metal PoolPark, R. J. / Kim, S. B. / Kim, H. D. / Choi, S. M. et al. | 1997
- 89
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- 114
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Feasibility of a Multi-Crucible Core-Catcher: Final Results of the StudySzabo, I. / Richard, P. et al. | 1997
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Large-Scale Experiments on Ex-Vessel Core Melt BehaviourSappok, M. / Steinwarz, W. et al. | 1997
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Experimental and Analytical Programs Investigating Cooling of a Continuous Mass of Relocated DebrisRempe, J. L. / Wolf, J. R. et al. | 1997
- 142
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Upgrading of Operating NPP Units Equipped with V- 179 and V-230 Reactors to Enhance Safety in Case of Severe Accidents Followed by Reactor Core and Reactor Vessel DestructionNigmatulin, B. I. / Fedorov, V. G. / Sidorov, A. S. / Nosenko, G. E. et al. | 1997
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- 248
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- 256
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Use of Probabilistic Risk Assessment to Improve RegulationRamey-Smith, A. / El-Bassioni, A. / Guttman, J. / Hardin, W. et al. | 1997
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- 269
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Key Issues Recently Treated Within the French-German Safety ApproachFrisch, W. / Gros, G. et al. | 1997
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- 306
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An Experimental Study of Steam Explosions Involving Chemically Reactive MetalCho, D. H. / Armstrong, D. R. / Gunther, W. H. / Basu, S. et al. | 1997
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Tests of Passive Catalytic Recombiners (PARS) for Combustible Gas Control in Nuclear Power PlantsBraillard, O. / Guieu, S. / Hosler, J. / Sliter, G. et al. | 1997
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Some Aspects of a Nuclear Safety of a Laser System Pumped with a Twin-Core Fast Burst ReactorBarzilov, A. P. / Dyachenko, P. P. / Gulevich, A. V. / Kukharchuk, O. F. et al. | 1997
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leakage Through Concrete-Steel Interfaces at and Around Containment Penetration Assemblies: Some New ObservationsChukrabarti, S. K. / Kumar, A. / Basu, P. C. et al. | 1997
- 1211
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Examination of the Behavior of Embedded Steel Plates in Concrete Containment Structures and Present Design MethodsChakrabarti, S. K. / Mishra, R. C. et al. | 1997
- 1219
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Model Experiments BERDA Describing the Impact of Molten Core Material Against a PWR Vessel HeadKrieg, R. / Malmberg, T. / Messemer, G. / Hoffman, G. et al. | 1997
- 1227
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Theoretical Models Describing the Impact Loading of a PWR Vessel HeadDolensky, B. / Goller, B. / Hirt, A. / Krieg, R. et al. | 1997
- 1237
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Application of Flow-Controllable Accumulator and Performance Analysis in Korean Nuclear Power PlantsJung, B.-R. / Lee, U.-C. et al. | 1997
- 1245
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ROSA-AP600 Experiment Simulating a Steam Generator Tube Rupture TransientNakamura, H. / Kukita, Y. / Ghan, L. S. / Schultz, R. R. et al. | 1997
- 1253
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The Effect of Flowrate of Subcooling Water on Boiling from Downward-Facing Curved SurfaceYefanov, A. D. / Kalyakin, S. G. / Grabezhnaya, V. A. / Grachev, N. S. et al. | 1997
- 1261
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Analyses of Steam Injector ExperimentsDumaz, P. / Mazzocchi, L. / Vanini, P. et al. | 1997
- 1268
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Experimental and Numerical Studies on Heat Transfer and Fluid Flow Characteristics in a Vacuum Vessel of Fusion Reactor After the Loss-of-Vacuum-Events OccurredTakase, K. / Kunugi, T. / Seki, Y. et al. | 1997
- 1276
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Evaluation of RELAP5/MOD3.1 to SPES-2 ExperimentsD'Auria, F. / Galassi, G. M. / Oriolo, F. / Fiorino, E. et al. | 1997
- 1286
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Optimization of the Safety Injection System for Korean Next Generation ReactorKyu Hwan Bae / Hong Sik Lim / Jin Ho Song / Jong Kyun Park et al. | 1997
- 1294
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Safety Depressurization System for Korean Next Generation ReactorYong Min Kwon / Hong Sik Lim / Jin Ho Song / Jong Kyun Park et al. | 1997
- 1305
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Innovative Containment Cooling for a Double Concrete ContainmentCavicchia, V. / Fiorino, E. / Vanini, P. et al. | 1997
- 1313
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Safety Features of Future LWR in Germany-Regulatory ViewBerg, H. P. / Weil, L. et al. | 1997
- 1320
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Conclusions from a Probabilistic Safety Analysis for FRJ-2 (DIDO) and Realization of Risk Minimization MeasuresWolters, J. / Nabbi, R. et al. | 1997
- 1328
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Reliability Testing of Shutdown System Software for Wolsong NPP 2, 3, and 4Hang Bae Kim et al. | 1997
- 1334
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The Origin of Pressure Inhomogeneities at Early Stages of Fuel-Coolant Interaction and Melt Fragmentation CriteriaGlaskov, V. V. / Sinkevich, O. A. / Nigmatulin, B. I. / Tsoy, V. R. et al. | 1997
- 1339
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Safety Management of a High Energy Accelerator Used in the Production of TritiumStark, R. M. / Allen, C. L. / Brown, N. W. et al. | 1997