Effect of Boric Acid Solubility in Steam on the Process of Mass Transfer during Emergency Cooling of VVER-1200 Nuclear Reactor

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dc.contributor.author Kabir Hridoy, Md. Rezouanul
dc.contributor.author A.V., Morozov
dc.contributor.author Kabir, Md Saif
dc.date.accessioned 2022-01-19T04:27:21Z
dc.date.available 2022-01-19T04:27:21Z
dc.date.issued 2021-12
dc.identifier.issn 2224-2007
dc.identifier.uri http://dspace.mist.ac.bd:8080/xmlui/handle/123456789/685
dc.description.abstract The mechanisms of boric acid mass transfer in a VVER-1200 reactor core are studied in this work in the event of a major circulatory pipeline rupture and loss of all AC power. The VVER-1200's passive core cooling technology is made up of two levels of hydro accumulators. They use boric acid solution with a concentration of 16 g H3BO3/kg H2O to control the reactivity. Because of the long duration of the accident process, the coolant with high boron content starts boiling and steam with low concentration of boric acid departs the core. So, conditions could arise in the reactor for possible accumulation and subsequent crystallization of boric acid, causing the core heat removal process to deteriorate. Calculations were carried out to estimate the likelihood of H3BO3 build-up and subsequent crystallization in the core of the VVER reactor. According to the calculations, during emergency the boric acid concentration in the reactor core is 0.153 kg/ kg and 0.158 kg/kg in both the events of solubility of steam and without solubility of steam respectively and it does not exceed the solubility limit which is about 0.415 kg/kg at water saturation temperature. No precipitation of boric acid occurs within this time during the whole emergency process. Therefore, findings of the study can be used to verify whether the process of decay heat removal is affected or not. en_US
dc.language.iso en en_US
dc.publisher R&D Wing, MIST en_US
dc.subject VVER-1200, Crystallization, Hydroaccumulator-1, 2, Boric Acid, Reactor Core en_US
dc.title Effect of Boric Acid Solubility in Steam on the Process of Mass Transfer during Emergency Cooling of VVER-1200 Nuclear Reactor en_US
dc.type Article en_US


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