Applicability of a mechanistic numerical method for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors

When pressurized water or vapor leaks from a failed heat transfer tube in a steam generator of sodium-cooled fast reactors, a high-velocity, high-temperature jet with sodium-water chemical reaction may cause wastage on the adjacent tubes. For assessment of the wastage environment, a mechanistic comp...

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Autores principales: Akihiro UCHIBORI, Hiroyuki OHSHIMA
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Lenguaje:EN
Publicado: The Japan Society of Mechanical Engineers 2016
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spelling oai:doaj.org-article:9109f0866cfe439cb9c972b602f19a362021-11-26T06:51:31ZApplicability of a mechanistic numerical method for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors2187-974510.1299/mej.15-00620https://doaj.org/article/9109f0866cfe439cb9c972b602f19a362016-03-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/3/3/3_15-00620/_pdf/-char/enhttps://doaj.org/toc/2187-9745When pressurized water or vapor leaks from a failed heat transfer tube in a steam generator of sodium-cooled fast reactors, a high-velocity, high-temperature jet with sodium-water chemical reaction may cause wastage on the adjacent tubes. For assessment of the wastage environment, a mechanistic computer code called SERAPHIM calculating compressible multicomponent multiphase flow with sodium-water chemical reaction has been developed. In this study, applicability of the SERAPHIM code was investigated through the analysis of the experiment on water vapor discharging in liquid sodium under actual condition of the steam generator. The computational domain consists of the cylindrical vessel and the simulated two horizontal heat transfer tubes. The cylindrical vessel was initially filled with liquid sodium. Pressurized water vapor goes into the sodium pool vertically upward from the discharging nozzle located at the center of one of the two tubes. The numerical result showed that the underexpanded jet appeared and impinged on the target tube located above the discharging tube. The calculated temperature distribution agreed with the measurement result well. The liquid droplet entrainment and its transport were considered in this analysis. The region with higher impingement velocity of the liquid droplet was close to the wastage region confirmed in the experiment.Akihiro UCHIBORIHiroyuki OHSHIMAThe Japan Society of Mechanical Engineersarticlesodium cooled fast reactorsteam generatorsodium water reactionfailure propagationmechanistic numerical methodMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 3, Iss 3, Pp 15-00620-15-00620 (2016)
institution DOAJ
collection DOAJ
language EN
topic sodium cooled fast reactor
steam generator
sodium water reaction
failure propagation
mechanistic numerical method
Mechanical engineering and machinery
TJ1-1570
spellingShingle sodium cooled fast reactor
steam generator
sodium water reaction
failure propagation
mechanistic numerical method
Mechanical engineering and machinery
TJ1-1570
Akihiro UCHIBORI
Hiroyuki OHSHIMA
Applicability of a mechanistic numerical method for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors
description When pressurized water or vapor leaks from a failed heat transfer tube in a steam generator of sodium-cooled fast reactors, a high-velocity, high-temperature jet with sodium-water chemical reaction may cause wastage on the adjacent tubes. For assessment of the wastage environment, a mechanistic computer code called SERAPHIM calculating compressible multicomponent multiphase flow with sodium-water chemical reaction has been developed. In this study, applicability of the SERAPHIM code was investigated through the analysis of the experiment on water vapor discharging in liquid sodium under actual condition of the steam generator. The computational domain consists of the cylindrical vessel and the simulated two horizontal heat transfer tubes. The cylindrical vessel was initially filled with liquid sodium. Pressurized water vapor goes into the sodium pool vertically upward from the discharging nozzle located at the center of one of the two tubes. The numerical result showed that the underexpanded jet appeared and impinged on the target tube located above the discharging tube. The calculated temperature distribution agreed with the measurement result well. The liquid droplet entrainment and its transport were considered in this analysis. The region with higher impingement velocity of the liquid droplet was close to the wastage region confirmed in the experiment.
format article
author Akihiro UCHIBORI
Hiroyuki OHSHIMA
author_facet Akihiro UCHIBORI
Hiroyuki OHSHIMA
author_sort Akihiro UCHIBORI
title Applicability of a mechanistic numerical method for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors
title_short Applicability of a mechanistic numerical method for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors
title_full Applicability of a mechanistic numerical method for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors
title_fullStr Applicability of a mechanistic numerical method for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors
title_full_unstemmed Applicability of a mechanistic numerical method for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors
title_sort applicability of a mechanistic numerical method for sodium-water reaction phenomena in steam generators of sodium-cooled fast reactors
publisher The Japan Society of Mechanical Engineers
publishDate 2016
url https://doaj.org/article/9109f0866cfe439cb9c972b602f19a36
work_keys_str_mv AT akihirouchibori applicabilityofamechanisticnumericalmethodforsodiumwaterreactionphenomenainsteamgeneratorsofsodiumcooledfastreactors
AT hiroyukiohshima applicabilityofamechanisticnumericalmethodforsodiumwaterreactionphenomenainsteamgeneratorsofsodiumcooledfastreactors
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