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Burman, D.L.; Olson, C.A.
Proceedings of a specialist meeting on the behaviour of water reactor fuel elements under accident conditions1977
Proceedings of a specialist meeting on the behaviour of water reactor fuel elements under accident conditions1977
AbstractAbstract
[en] A statistical method for predicting burst and blockage magnitude and distribution has been developed. This method can be used to evaluate blockage during a LOCA, predict the results of multi-rod burst tests, or provide a rationale for extrapolating the results of small cluster tests to large arrays. An analysis of actual fabrication data establishes a realistic pellet-to-pellet temperature and power uncertainly which is much smaller than normally used in safety analyses but which is more appropriate in predicting flow blockage distributions. With this derived statistical method, sensitivities to the various parameters used are investigated and representative flow blockages calculated for the hot assembly of a Westinghouse PWR plant
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Source
Organisation for Economic Co-Operation and Development - Nuclear Energy Agency, Committee on the safety of nuclear installations - OECD/NEA/CSNI, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France); 774 p; 1977; p. 157-181; Specialist meeting on the behaviour of water reactor fuel elements under accident conditions; Spaatind (Norway); 13-16 Sep 1976
Record Type
Report
Literature Type
Conference
Report Number
Country of publication
ACCURACY, CLADDING, DEFORMATION, FLOW BLOCKAGE, FUEL ELEMENT FAILURE, FUEL RODS, FUEL-CLADDING INTERACTIONS, LOSS OF COOLANT, NEA, PWR TYPE REACTORS, REACTOR ACCIDENT SIMULATION, REACTOR COOLING SYSTEMS, REACTOR SAFETY, STATISTICAL MODELS, SYSTEM FAILURE ANALYSIS, TEMPERATURE DISTRIBUTION, THERMAL HYDRAULICS
ACCIDENTS, COOLING SYSTEMS, DEPOSITION, ENERGY SYSTEMS, ENRICHED URANIUM REACTORS, FAILURES, FLUID MECHANICS, FUEL ELEMENTS, HYDRAULICS, INTERNATIONAL ORGANIZATIONS, MATHEMATICAL MODELS, MECHANICS, OECD, POWER REACTORS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, SAFETY, SIMULATION, SURFACE COATING, SYSTEMS ANALYSIS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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