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Reil, K.O.; Young, M.F.
Proceedings of the fourth CSNI specialist meeting on fuel-coolant interaction in nuclear reactor safety - Volumes 2+31979
Proceedings of the fourth CSNI specialist meeting on fuel-coolant interaction in nuclear reactor safety - Volumes 2+31979
AbstractAbstract
[en] The Prompt Burst Energetics (PBE) program is part of the Advanced Reactor Safety Research Program conducted by Sandia Laboratories. These studies involve an in-pile experimental program and complementary analytical investigation of the energetic response of important reactor fuel-clad-coolant systems subjected to energy deposition conditions associated with super-prompt critical excursions. The objectives of the present program include identification and characterization of the phenomena which dominate the conversion of thermal energy to work, development of models which accurately predict the energetics associated with such hypothetical accidents, and provision of the necessary input data for those models. This program includes the examination of the integral effects of fuel-clad-coolant interactions, fission gas release, and fuel and fission product vapor pressure during super-prompt critical core disruptive conditions, and thus, serves to define the initial conditions for hydrodynamic expansion of the disrupted core. To date, eighteen single-pin PBE experiments have been completed. An important conclusion drawn from the PBE work to date is that FCIs do occur in both the UO2/Na and UC/Na systems under simulated LMFBR accident conditions. This paper presents a description of the PBE experiment methods, discusses the results of four sodium-in experiments and associated interpretive analysis, and substantiates the conclusions drawn from those results. An outline of future PBE experimental work is also given
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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); 493 p; Oct 1979; p. 251-268; 4. CSNI specialist meeting on fuel-coolant interaction in nuclear reactor safety; Bournemouth (United Kingdom); 2-5 Apr 1979; 13 refs.
Record Type
Report
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Conference
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Country of publication
BENCH-SCALE EXPERIMENTS, ENERGY YIELD, EXPLOSIONS, FLUID FLOW, FRAGMENTATION, FUEL PINS, FUEL-COOLANT INTERACTIONS, HEAT TRANSFER, LMFBR TYPE REACTORS, MOLTEN METAL-WATER REACTIONS, NEA, PRESSURE MEASUREMENT, PULSATIONS, REACTOR ACCIDENT SIMULATION, REACTOR ACCIDENTS, REACTOR SAFETY, REACTOR SAFETY EXPERIMENTS, SANDIA NATIONAL LABORATORIES, SODIUM, URANIUM DIOXIDE, USA
ACCIDENTS, ACTINIDE COMPOUNDS, ALKALI METALS, BREEDER REACTORS, CHALCOGENIDES, DEVELOPED COUNTRIES, ELEMENTS, ENERGY TRANSFER, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FUEL ELEMENTS, INTERNATIONAL ORGANIZATIONS, LIQUID METAL COOLED REACTORS, METALS, NATIONAL ORGANIZATIONS, NORTH AMERICA, OECD, OXIDES, OXYGEN COMPOUNDS, REACTOR COMPONENTS, REACTORS, SAFETY, SIMULATION, URANIUM COMPOUNDS, URANIUM OXIDES, US DOE, US ORGANIZATIONS
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