Proceedings of the International Meeting on FAST REACTOR SAFETY AND RELATED PHYSICS October 5-8, 1976 Chicago, Illinois VolumeⅡ: LICENSING;SAFETY-RELATED DESIGN

摘要

LMFBR Accident Energetics and Their Role in LicensingnSafety Related Design Philosophy and Experience of the Experimental Fast Reactor JOYOnResolution of Key Safety-Related Issues in FFTF Regulatory ReviewnDevelopment of Technical Specifications for EBR-Ⅱ: Some Considerations for Application to Commercial LMFBR'snDesigning for Safety in Fast Reactors in the Presence of UncertaintiesnDesign-Related Inherent Safety Characteristics in Large LMFBR Power PlantsnThe Decay Heat Removal Plan of the §NJR-300-A Licensed ConceptnDesign Requirements for the SNR-300 Containment SystemnComparison of Neutronics Calculations in a Loss-of-Flow AccidentnAn Assessment of Transport Effects in LMFBR Safety NeutronicsnNeutronic Coupling of Feedback EffectsnRecent Improvements in the Prediction of Reactivity Coefficients Relevant to LMFBR Accident AnalysisnStatus of Safety-Related FETF Neutronics ParametersnOn the Extrapolation of ZPR, Sodium Void Measurements to the Power ReactornExperimental Studies of GCER, Safety Physics Parameters in the ZPR-9 Critical AssembliesnAnalysis of Safety-Related Physics Measurements in the Initial GCER Critical ExperimentsnEffect of Steam Entry in a GCFR Core