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Experimental data on heat flux distribution from a volumetrically heated pool with frozen boundaries
Helle, Maria; Kymaelaeinen, Olli; Tuomisto, Harri
Proceedings of the Workshop on in-vessel core debris retention and coolability1999
Proceedings of the Workshop on in-vessel core debris retention and coolability1999
AbstractAbstract
[en] The COPO II experiments are confirmatory experiments and a continuation project to the earlier COPO I experiments. As in COPO 1, a molten corium pool on the lower head of a RPV is simulated by a two - dimensional slice of it in linear scale 1:2. The corium is simulated by water-zinc sulfate solution with volumetric Joule heating. The heat flux distribution on the boundaries and the temperature distribution in the pool are measured. The major new feature in COPO II is the cooling arrangement which is based on circulation of liquid nitrogen on the outside of the pool boundaries. The use of liquid nitrogen leads to formation of ice on the inside of boundaries. Two geometrically different versions of the COPO II facility have been constructed: one with a tori-spherical bottom shape, simulating the RPV of a VVER-440 reactor as COPO I, and another one with semicircular bottom simulating a western PWR such as AP600. The modified Rayleigh number in the COPO II experiments corresponds to the one in a prototypic corium pool (∼ 1015). This paper reports results from the COPO II-Lo and COPO II-AP experiments with homogenous pool. Results indicate that the upward heat fluxes are in agreement with the results of the COPO I experiments. Also, as expected, the time averaged upward heat flux profile was relatively flat. On the other hand, the heat fluxes at the side and bottom boundaries of the pool were slightly higher in COPO II-Lo than in COPO I. In COPO II-AP, the average heat transfer coefficients to the curved boundary were higher than predicted by Jahn's and Mayinger's correlation, but slightly lower than in BALI experiments. (authors)
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Organisation for Economic Co-Operation and Development, Nuclear Energy Agency - OECD/NEA, Committee on the safety of nuclear installations - CSNI, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France); 409 p; 25 Feb 1999; p. 169-179; Workshop on in-vessel core debris retention and coolability; Garching (Germany); 3-6 Mar 1998; 11 refs.
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Report
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Conference
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ACCIDENT MANAGEMENT, CONTAINMENT SYSTEMS, COOLING, CORE FLOODING SYSTEMS, CORIUM, HEAT FLUX, HEAT TRANSFER, PWR TYPE REACTORS, RAYLEIGH NUMBER, REACTOR ACCIDENTS, REACTOR COOLING SYSTEMS, REACTOR CORES, REACTOR EXPERIMENTAL FACILITIES, REACTOR VESSELS, TEMPERATURE DISTRIBUTION, THERMAL HYDRAULICS, WWER TYPE REACTORS, ZINC SULFATES
ACCIDENTS, CONTAINERS, CONTAINMENT, COOLING SYSTEMS, DIMENSIONLESS NUMBERS, ECCS, ENERGY SYSTEMS, ENERGY TRANSFER, ENGINEERED SAFETY SYSTEMS, ENRICHED URANIUM REACTORS, FLUID MECHANICS, HYDRAULICS, MANAGEMENT, MECHANICS, OXYGEN COMPOUNDS, POWER REACTORS, PWR TYPE REACTORS, REACTOR COMPONENTS, REACTOR PROTECTION SYSTEMS, REACTORS, SULFATES, SULFUR COMPOUNDS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS, ZINC COMPOUNDS
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