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Proceedings of the International Meeting on FAST REACTOR SAFETY AND RELATED PHYSICS October 5-8,1976 Chicago, Illinois Volume Ⅲ: ACCIDENT ANALYSIS;STRUCTURAL DYNAMICS


CECA ctivities in the Field of LMEBR SafetynA Method for Assessing Core-Wide Incoherency Effects on LMFBR Whole-Core Accident EvolutionnThe Transition Phase in LMFBR Hypothetical AccidentsnAn Assessment of Fuel Failure Propagation in LMFBRSnDepressurization Accident Studies for GCFR'snComputational Analysis of Fuel-Sodium Interactions with an Improved MethodnProbabilistic Analysis of Accidental Transients in an LMFBRnEffect of Failure Incoherence in a LMFBR Hypothetical Overpower AccidentnAnalysis of LMFBR Overpower Accident, Including Fission Gas Effects in the Predisassembly and Disassembly PhasenComparison of SAS3Aand MELJ-ⅢPredictions for a Transient Overpower Hypothetical AccidentnEPIC: A Computer Program for Fuel-Coolant InteractionsnFuel Cladding Mechanical Properties for Transient AnalysisnAnalytic Models for Fuel Pin Transient PerformancenFuel Pin Failure Models and Fuel-Failure Thresholds for Core Disruptive Accident AnalysisnSafety Issues for Advanced-Fueled LMFBRsnBehavior of Carbide Fuel in Local and Whole Core AccidentsnSafety Problems Related to Microheterogeneities in Physically Mixed Oxide FuelsnCentral Computerized Data Base for Liquid Metal Fast Breeder Reactor Safety CodesnC. N. Kelber (USNRC) Influence of Fuel-Coolant-lnteractions on Loss of Flow Type Core Disruptive Accidents for the SNR-300nUnprotected Loss-of-Flow Transients in LargeJLMFBRsnTreatment of Incoherencies and Uncertainties in LMFBR LOF Accident Analysis with PARSECnPipe Rupture Studies for the CRBR Using DEMO and SASnAnalysis of Postulated FFTE Pipe RupturesnWork-Energy Characterization for Core-Disruptive AccidentsnExperimental Comparison Studies with the VENUS-II Disassembly CodenA Computational Model for Analyzing Postulated LMFBR Accident Fuel Boil-Up ConditionsnCritical Configurations and Secondary Excursions for High Temperature Fuel/Steel MixturesnLMFBR Disassembly AnalysesnRole of Wall Heat Transfer and Other System Variables on Fuel Compaction and RecriticalitynAccident Termination by Element Dropout in the GCFRnSIMMER-1, an LMFBR Disrupted Core Analysis CodenAnalyses of LMFBR Core Disruption and Accident Phenomena Using the SIMMER-I CodenLarge-Scale Deterministic Computer Code Systems and LMFBR Safety: A PerspectivenThe SAS4A LMFBR Accident Analysis Code System: A Progress ReportnMolten Fuel Motion During a Fast-Reactor Overpower TransientnMulti-Field Hydrodynamic Disassembly Calculations with Space-Time Kinetics: FX2/VENUS-ⅢnCore Disruptive Accident and Recriticality Analysis with FX2-POOLnAn Eulerian Finite Element Method for Unsteady Compressible Flow ProblemsnA Probabilistic/Deterministic Procedure for Analyzing LMFBR Core Disruptive AccidentsnIntroductory RemarksnA Generalized Eulerian Method in Reactor Containment Analysis and Its Comparison with Other Numerical MethodsnEvaluation of Explicit Finite-Difference Techniques for LMFBR Safety AnalysisnAn Experimental Programme to Validate Wave Propagation and Fluid Flow Codes for Explosion Containment AnalysisnSimulation of Hypothetical Core Disruptive Accidents in Vessel ModelsnA Comparison of ANL Containment Codes with SNR.-300 Simulation ExperimentsnSafety Analysis of the Primary Heat Transport Systems of LMFBRsnSome Aspects of the Structural Response of Pool-Type LMFBR Systems to HCDA and Seismic EventsnOn the Fuel-Clad Stress-Strain State at the Beginning of a TransientnPrediction of High Strain-Rate Deformation of LMFBR Cladding during Reactor TransientsnThe Response of Single Subassembly Hexcan Wrappers to Pressure LoadsnDevelopment of Models for Dynamics of Subassembly Can Walls during Core DisruptionnAnalytic Studies of Subassembly Failure PropagationnStress Intensity Factors for Corner-Cracked Subassembly DuctsnExplosion Tests on LMFBR-Core Models;An Evaluation for Reactor SafetynFinite Element Solution of Transient Fluid-Structure Problems in Lagrangian Coordinates......

【关 键 词】: Proceedings of the International Meeting on FAST REACTOR SAFETY AND RELATED PHYSICS October 5-8, 1976 Chicago, Illinois Volume Ⅲ: ACCIDENT ANALYSIS, STRUCTURAL DYNAMICS
【期刊论文数据库】: [DBS_Articles_01]
【期刊论文编号】: 104,848,742
【摘要长度】: 3,893
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