Zobrazeno 1 - 10
of 12
pro vyhledávání: '"Yuejian Luo"'
Autor:
Jian Deng, Dahuan Zhu, Yuejian Luo, Hongping Sun, Ming Zhang, Lili Liu, Qingan Xiang, Xiaoli Wu, Youyou Xu, Qingwen Xiong
Publikováno v:
Frontiers in Energy Research, Vol 10 (2022)
Understanding a reliable description of the heat transfer in the molten pool with three-layer configuration is inevitable for the design of severe accident mitigation measures in research reactors, such as IVR-ERVC. However, investigations on a thick
Externí odkaz:
https://doaj.org/article/551030b0d4374745808b89de9a23884f
Publikováno v:
Frontiers in Energy Research, Vol 10 (2022)
When the large pressurized water reactor in-vessel retention (IVR) system is put into operation, the outer wall of the reactor pressure vessel (RPV) will experience severe temperature fluctuations and be subjected to high internal pressure loads at t
Externí odkaz:
https://doaj.org/article/a0256da3b3e5409383c0023d154c3f39
Publikováno v:
Volume 11: Mitigation Strategies for Beyond Design Basis Events.
Cladding oxidation is a particularly important process which can affect the process of core melting. Synchronously, hydrogen released from zircaloy-water reaction is a threat to the integrity of containment. Up to now, multifarious zircaloy-water oxi
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b96afb4ef480981ad45635226e84b3e4
https://doi.org/10.1115/icone29-92396
https://doi.org/10.1115/icone29-92396
Autor:
Yuejian Luo, Jian Deng, Dahuan Zhu, Hongping Sun, Ming Zhang, Xiaoli Wu, Youyou Xu, Lili Liu, Wenzhen Hu, Qingan Xiang
Publikováno v:
Volume 11: Mitigation Strategies for Beyond Design Basis Events.
U-Al alloy fuels have been applied in research reactors, and it is different from typical pressurized water reactors in geometry and components. This paper conducts a theoretical analysis on migration behavior of molten material in U-Al alloy fuels,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ac5031bed64250867823d559ac510142
https://doi.org/10.1115/icone29-93467
https://doi.org/10.1115/icone29-93467
Publikováno v:
Annals of Nuclear Energy. 126:1-9
As an effective severe accident mitigation strategy, in-vessel retention – external reactor vessel cooling (IVR-ERVC) has been applied to some advanced nuclear reactors. In the assessment of AP600-like reactor, the risk oriented accident analysis m
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6780c03ce0d8f062e24c92ba57f329bc
https://doi.org/10.1016/j.anucene.2018.11.003
https://doi.org/10.1016/j.anucene.2018.11.003
Autor:
Hongping Sun, Jian Deng, Yuejian Luo, Ming Zhang, Youyou Xu, Xiaoli Wu, Lili Liu, Suizheng Qiu, G.H. Su
Publikováno v:
Annals of Nuclear Energy. 169:108940
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::688c8f474ff4f71d3438a590ba86e5f3
https://doi.org/10.1016/j.anucene.2021.108940
https://doi.org/10.1016/j.anucene.2021.108940
Autor:
Qingwen Xiong, Peng Du, Jian Deng, Daishun Huang, Gongle Song, Libo Qian, Zenghui Wu, Yuejian Luo
Publikováno v:
Reliability Engineering & System Safety. 221:108337
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b5b7a51e44409f41031c1eba32a8b7b4
https://doi.org/10.1016/j.ress.2022.108337
https://doi.org/10.1016/j.ress.2022.108337
Autor:
Lili Liu, Jian Deng, Ming Zhang, Liang Chen, Youyou Xu, Yuejian Luo, Yang Li, Hongping Sun, Hongxing Yu, Houjun Gong
Publikováno v:
Progress in Nuclear Energy. 146:104128
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9633d387c6317abf674877ec9c9fdab8
https://doi.org/10.1016/j.pnucene.2022.104128
https://doi.org/10.1016/j.pnucene.2022.104128
Publikováno v:
Progress in Nuclear Energy. 145:104125
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::715391ec0f6f22917d4ab75db2b8cdda
https://doi.org/10.1016/j.pnucene.2022.104125
https://doi.org/10.1016/j.pnucene.2022.104125
Publikováno v:
Progress in Nuclear Energy. 109:74-82
In-vessel retention (IVR) in the manner of external reactor vessel cooling (ERVC) is an important severe accident mitigation strategy, which has been applied to some advanced light water reactors, e.g. AP1000. This main assessment method on the effec
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3f2d5004bad2e63dd7e904e8111a8542
https://doi.org/10.1016/j.pnucene.2018.07.013
https://doi.org/10.1016/j.pnucene.2018.07.013