Journal of Nuclear Science and Technology · 2002 · 29 citations · 10 references
EngineeringNuclear EngineeringNuclear MaterialsNuclear Safety AnalysisSafety EngineeringFuel IntegrityMixed Oxide FuelReactor Core DesignReactor DesignThermal-hydraulic Safety AnalysisAccident Scenario AnalysisCompact Reactor DesignCore Heat Transfer Under Accident ConditionsGeneral BehaviorReactor Core Damage ProgressionReactor Core DynamicsRecriticality Analysis
General behavior principles (GBPs) first introduced in 1976 (H. K. Fauske, the Role of Core-Disruptive Accidents in Design and Licensing of LMFBRs, Nuclear Safety, Vol. 17, No. 5, 550–567, 1976) are applied to assess the core disruptive accident (CDA) outcome for a large (3,500MWt) high power density oxide-fueled sodium-cooled fast breeder reactor (FBR). Non-energetic termination in the so-called Initiating Phase is emphasized and is made possible by considering departures from the traditional core design including the Subassembly Inner Duct and Limited Blanket Removal concepts. This early accident scenario termination eliminates potential concerns raised related to recriticality events and also facilitates the potential for in-vessel fuel debris coolability for the large FBR with a compact reactor vessel.
10
Dryout Heat Fluxes for Inductively Heated Particulate Beds
Vijay K. Dhir, I. Catton · Journal of Heat Transfer · 1977 · 48 citations
Engineering, Physics, Heat Transfer +11
Transient Freezing of a Flowing Ceramic Fuel in a Steel Channel
Michael Epstein, M. A. Grolmes, Robert E. Henry et al. · Nuclear Science and Engineering · 1976 · 37 citations