Experimental research on the small scale bubble condenser model
Description
A special pressure suppression system was designed to minimize the consequences of loss-of-coolant accidents for WWER 440/V-213 type reactors. The experimental facility is described consisting of a high pressure and a low pressure part. To measure the pressure and pressure differences on the high pressure part, induction probes were used with compensation up to 100oC. For the low pressure part the Rosemount capacity pressure transducers were applied. The reduction of fluid weight in the vessel was determined by a strain gauge dynamometer. During experiments, main attention was focused on verification of the performance of the bubble condenser under mass loads higher than those specified in the project, on verification of the performance and significance of auxiliary fittings, on provision of data for the testing of computer codes, on completion of knowledge of the physical processes in the bubble condenser, and on documentation of the reproducible character of the experiments used by the designer in application of the bubble condenser in the accident localisation system. All experiments performed with the bubble condenser showed that with this method and arrangement no acoustic phenomena occurred during the condensation phase. (J.B.)
Additional details
Publishing Information
- Imprint Title
- Proceedings of the international topical meeting on VVER safety
- Imprint Pagination
- 416 p.
- Journal Page Range
- p. 84-86.
- Report number
- INIS-mf--14715
Conference
- Title
- International topical meeting on VVER safety.
- Dates
- 21-23 Sep 1995.
- Place
- Prague (Czech Republic).
INIS
- Country of Publication
- Czech Republic
- Country of Input or Organization
- Czech Republic
- INIS RN
- 27022814
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONDENSER COOLING SYSTEMS; FUNCTIONAL MODELS; LOSS OF COOLANT; PERFORMANCE TESTING; PRESSURE SUPPRESSION; SIMULATION; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; AUXILIARY SYSTEMS; AUXILIARY WATER SYSTEMS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS