Zobrazeno 1 - 6
of 6
pro vyhledávání: '"Yiji YE"'
Publikováno v:
Mechanical Engineering Journal, Vol 11, Iss 1, Pp 23-00491-23-00491 (2024)
Buckling is a critical failure mode of the Fast Reactor Main Vessel (FRMV) subjected to seismic load. Post-buckling stability of FRMV is a crucial safety issue during excessive earthquakes. Our prior study revealed that global response becomes stable
Externí odkaz:
https://doaj.org/article/b233f6fcd106434490caed28cbfce99d
Autor:
Ting Zhang, Songbai Cheng, Yuhang Dong, Yunhao Chen, Chuiyi Meng, Xiaolin Chen, Ting Zhu, Yiji Ye
Publikováno v:
Annals of Nuclear Energy. 132:258-270
From the past analyses of Core Disruptive Accidents (CDA) for sodium-cooled fast reactors, it has been recognized that with the assumption of very pessimistic conditions, a large-scale molten-fuel pool, which contains sufficient amount of fuel to ach
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4db3e23190496bc66e4db9378b249fda
https://doi.org/10.1016/j.anucene.2019.04.048
https://doi.org/10.1016/j.anucene.2019.04.048
Experimental study on pressurization characteristics of a water droplet entrapped in molten LBE pool
Publikováno v:
Nuclear Engineering and Design. 378:111192
In a postulated Steam Generator Tube Rupture (SGTR) accident of pool-type Lead-cooled Fast Reactor (LFR), highly-pressurized water from the secondary circuit will be discharged into the primary vessel containing low-pressure molten lead-based alloy (
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::4c69357f929869be654c8fb2558bcbbf
https://doi.org/10.1016/j.nucengdes.2021.111192
https://doi.org/10.1016/j.nucengdes.2021.111192
Publikováno v:
Nuclear Engineering and Design. 371:110943
In this study, to enhance the understanding of the thermo-hydraulic characteristics during the direct contact of molten lead-bismuth eutectic (LBE) and water, a series of visualized fragmentation experiments were conducted by releasing molten LBE int
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0eadc3e673c0e767b9dae38a016f571f
https://doi.org/10.1016/j.nucengdes.2020.110943
https://doi.org/10.1016/j.nucengdes.2020.110943
Publikováno v:
Annals of Nuclear Energy. 149:107760
In a Core Disruptive Accident (CDA) of Sodium-cooled Fast Reactor (SFR), by supposing rather pessimistic condition, a large molten fuel pool would be possibly formed that contains enough fuel with the potential to exceed prompt criticality due to fue
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3ce82f8475e4784754697cf63905024b
https://doi.org/10.1016/j.anucene.2020.107760
https://doi.org/10.1016/j.anucene.2020.107760
Publikováno v:
Annals of Nuclear Energy. 148:107705
Investigations on melt-jet behavior during Core Disruptive Accidents (CDAs) of Sodium-cooled Fast Reactors (SFR) are crucial to the design of In-Vessel Retention (IVR) strategy. In present work, aimed to achieve a comprehensive understanding on this
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cb27f340473ba8b81ecfc21b45afe8bf
https://doi.org/10.1016/j.anucene.2020.107705
https://doi.org/10.1016/j.anucene.2020.107705