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Bandurski, T.; Ezsoel, G.; Maroti, L.; Toth, I.
Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 11989
Fourth international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4). Proceedings. Vol. 11989
AbstractAbstract
[en] Experiments have been performed with the PMK integral-type facility, a model of WWER-440 type PWRs, to investigate two-phase natural circulation behaviour. The phenomena to be expected in this reactor type are different from those in PWRs with vertical steam generators mainly due to the loop seal in the hot leg and the horizontal layout of the steam generator heat transfer tubes. The experiments showed that the system is repressurized when the water level drops to the hot leg elevation due to the effect of the loop seal. Opening of the loop seal can be smooth, but may lead to oscillations depending on the power and the mass inventory. Natural circulation recovers after the hot leg loop seal is opened, but then decreases with further mass inventory decrease. (orig.)
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Source
Mueller, U.; Rehme, K.; Rust, K. (eds.); 745 p; ISBN 3-7650-1115-0; ; 1989; p. 478-483; Braun; Karlsruhe (Germany, F.R.); 4. international topical meeting on nuclear reactor thermal-hydraulics (NURETH-4); Karlsruhe (Germany, F.R.); 10-13 Oct 1989
Record Type
Book
Literature Type
Conference
Country of publication
ACCIDENTS, CONVECTION, COOLING SYSTEMS, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, FLUID FLOW, HEAT TRANSFER, PHYSICAL PROTECTION DEVICES, POWER REACTORS, PWR TYPE REACTORS, REACTOR ACCIDENTS, REACTOR COOLING SYSTEMS, REACTORS, THERMAL REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS, WWER TYPE REACTORS
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