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Thermal-hydraulic calculations for technical condition and lifetime extension assessment of SUNPP-3 reactor

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dc.contributor.advisor Мазурок, Олександр
dc.contributor.author Kravchenko, Volodymyr
dc.contributor.author Mykhailenko, Oleksandr
dc.contributor.author Mazurok, Oleksandr
dc.contributor.author Кравченко, Володимир Петрович
dc.contributor.author Кравченко, Владимир Петрович
dc.contributor.author Мазурок, Александр
dc.contributor.author Михайленко, Олександр
dc.contributor.author Михайленко, Александр
dc.date.accessioned 2019-11-29T06:51:21Z
dc.date.available 2019-11-29T06:51:21Z
dc.date.issued 2019-08-18
dc.identifier.citation Mazurok, O., Mykhailenko, O., Kravchenko, V. (2019). Thermal-hydraulic calculations for technical condition and lifetime extension assessment of SUNPP-3 reactor. Proceeding of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019, Portland, OR, august 18-22 2019, p. 1998-2011. en
dc.identifier.citation Mazurok, O. Thermal-hydraulic calculations for technical condition and lifetime extension assessment of SUNPP-3 reactor / O. Mazurok, O. Mykhailenko, V. Kravchenko // Proceeding of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-18, Portland, OR, august 18-22, 2019. – Portland, 2019. – P. 1998-2011. en
dc.identifier.uri http://dspace.opu.ua/jspui/handle/123456789/9713
dc.description.abstract This paper presents the results of thermal-hydraulic calculations performed as part of the technical condition and lifetime extension assessment of SUNPP-3 reactor. Based on the recommendations of the IAEA and the results of previously performed computational analyzes, the main conservative assumptions for the analysis of the selected computational scenarios were identified. These assumptions, in the form of initial and boundary conditions, were used in thermal-hydraulic analysis analyzes. When choosing the initial and boundary conditions for each scenario, were used the results of preliminary variant computational analyzes, engineering assessment of the initial and boundary conditions influence to the results, as well as experience in performing similar work. Thermal-hydraulic analyzes were performed using a computer code RELAP5 using a reactor model with a detailed breakdown of the downcomer and engineering code GRS-MIX to account for stratification in reactor downcomer. The results of analyzes showed that the selected initiating events lead to an intensive cooling down of the reactor pressure vessel and the internals. For scenarios leading to asymmetrical cooling, a different configuration of the ECCS was considered. For scenarios leading to a general cooling down of the coolant, the rupture location was chosen in such a way as to obtain maximum cooling down when the ECCS pumps operate in non-emergency loops. As a result of performing thermal-hydraulic analyzes of the initial events were determined boundary conditions for strength analysis performing. These boundary conditions were distribution of the pressure, the coolant temperature and the heat transfer coefficients. en
dc.language.iso en_US en
dc.publisher Proceeding of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019. en
dc.subject KEYWORDS Reactor pressure vessel, thermal shock, thermal-hydraulic, lifetime extension, downcomer en
dc.title Thermal-hydraulic calculations for technical condition and lifetime extension assessment of SUNPP-3 reactor en
dc.title.alternative Thermal-hydraulic calculations for technical condition and lifetime extension assessment of SUNPP-3 reactor en
dc.type Article in Scopus en
opu.kafedra Кафедра атомних електричних станцій uk
opu.citation.firstpage 31 en
opu.citation.conference Proceeding of 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 en
opu.staff.id kravchenko@opu.ua en
opu.conference.dates 18-22 2019 en


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