Zobrazeno 1 - 10
of 12
pro vyhledávání: '"Hanbee Na"'
Publikováno v:
Progress in Nuclear Energy. 161:104691
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::921af7d6c4c5f2be60877c2c32ca5c92
https://doi.org/10.1016/j.pnucene.2023.104691
https://doi.org/10.1016/j.pnucene.2023.104691
Publikováno v:
Journal of Mechanical Science and Technology. 35:3211-3221
Flow boiling experiments in microchannels under low mass fluxes have rarely been reported in the literature. In this study, flow boiling critical heat flux (CHF) for a parallel straight copper microchannel heat sink with 41 channels and hydraulic dia
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::35e4b6b2f64c2929553e655a48c190ce
https://doi.org/10.1007/s12206-021-0641-x
https://doi.org/10.1007/s12206-021-0641-x
Publikováno v:
Annals of Nuclear Energy. 183:109602
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b2b6dfb83f1e851b1b1dafd5f14d736c
https://doi.org/10.1016/j.anucene.2022.109602
https://doi.org/10.1016/j.anucene.2022.109602
Publikováno v:
Annals of Nuclear Energy. 178:109342
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1b37cded7511a06c036fb7a344f76ebb
https://doi.org/10.1016/j.anucene.2022.109342
https://doi.org/10.1016/j.anucene.2022.109342
Publikováno v:
Annals of Nuclear Energy. 124:245-256
Turbulent thermal mixing is one of the major degradation mechanisms of thermal fatigue, called high cycle thermal fatigue, and a mixing tee has been known as typical component susceptible to high cycle thermal fatigue. From a numerical analysis point
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4a8ec1c6ec52f1f0652e29f298fbff42
https://doi.org/10.1016/j.anucene.2018.10.006
https://doi.org/10.1016/j.anucene.2018.10.006
Publikováno v:
Annals of Nuclear Energy. 160:108363
This study assesses whether the integrity of a containment maintains during ex-vessel cooling when a molten corium spreads on a dry reactor cavity floor and then it is cooled by top water flooding in the case of a postulated severe accident in an APR
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::eb945a35d7e090c0497daabd862752bb
https://doi.org/10.1016/j.anucene.2021.108363
https://doi.org/10.1016/j.anucene.2021.108363
Publikováno v:
Annals of Nuclear Energy. 106:256-270
We present a preliminary study on the feasibility of the pre-flooded cavity strategy for ex-vessel cooling of APR1400 NPPs. Fragmented particles form a porous debris bed, so understanding the heat transfer mechanism in a porous medium and its critica
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5f28f9c127228ccc31806ec71674d34f
https://doi.org/10.1016/j.anucene.2017.03.025
https://doi.org/10.1016/j.anucene.2017.03.025
Publikováno v:
Progress in Nuclear Energy. 97:139-152
This preliminary study examines the feasibility of adopting a post-flooding strategy as molten corium cooling for APR1400 plants. We address negative effects of a steam explosion and unevenly spread corium that are associated with the current pre-flo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::728819aa9c2f284203e20b3ac3e709b9
https://doi.org/10.1016/j.pnucene.2016.12.017
https://doi.org/10.1016/j.pnucene.2016.12.017
Publikováno v:
Annals of Nuclear Energy. 151:107838
We develop an analytical model about concrete ablation during ex-vessel cooling in a pre-flooded cavity. The model considers the melting of dry debris bed, the formation of crust, the growth of crust and the thermal ablation of concrete. This model c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4b5da5bff8323ac0e1d17727480e1bb1
https://doi.org/10.1016/j.anucene.2020.107838
https://doi.org/10.1016/j.anucene.2020.107838
Publikováno v:
Annals of Nuclear Energy. 138:107123
This paper presents a feasibility study on a pre-flooded cavity strategy for cooling molten corium in OPR1000 nuclear power plants. The characteristics of debris beds formed in the pre-flooded reactor cavity are assumed to be the same as COOLOCE-8 BE
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::111f5f3a93533273930eae0cc8f122a5
https://doi.org/10.1016/j.anucene.2019.107123
https://doi.org/10.1016/j.anucene.2019.107123