Zobrazeno 1 - 10
of 14
pro vyhledávání: '"Tianzhou, Ye"'
Publikováno v:
International Journal of Advanced Nuclear Reactor Design and Technology, Vol 5, Iss 1, Pp 1-8 (2023)
The nanoscale liquid sodium film inside the microporous wick structure is of great importance to understanding the evaporation mechanism of the sodium heat pipe. The novel optimized wick structure is made of several layers of special screen. The surf
Externí odkaz:
https://doaj.org/article/9adecf25d740475883d13f8f483137d5
Autor:
Tianzhou, Ye, Jingyuan, Sun, Zhengliang, Huang, Yao, Yang, Binbo, Jiang, Jingdai, Wang, Yongrong, Yang
Publikováno v:
In Chemical Engineering Journal 1 September 2023 471
Autor:
Jiancheng Zhou, Tianzhou Ye, Dalin Zhang, Gongle Song, Rulei Sun, Jian Deng, Wenxi Tian, G.H. Su, Suizheng Qiu
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 1, Pp 61-68 (2021)
Experiments of vertically upward steam-water two-phase flow have been carried out in single-side heated narrow rectangular channel with a gap of 3 mm. Flow patterns were identified and classified through visualization directly. Slug flow was only obs
Externí odkaz:
https://doaj.org/article/cb4e78ef2610479d8834829190b45444
Publikováno v:
Nanomaterials, Vol 13, Iss 4, p 631 (2023)
FeCrAl alloys have been suggested as one of the most promising fuel cladding materials for the development of accident tolerance fuel. Creep is one of the important mechanical properties of the FeCrAl alloys used as fuel claddings under high temperat
Externí odkaz:
https://doaj.org/article/22f2559d48b94b74b6425204751d1fd2
Publikováno v:
Materials & Design, Vol 206, Iss , Pp 109766- (2021)
FeCrAl alloys have been proposed as nuclear fuel cladding materials in hope of offering great potential in accident tolerance for light water reactors. However, only a limited amount of data has been published on their creep properties. This work aim
Externí odkaz:
https://doaj.org/article/683381a214c94e4bbdf2ecb998f3e5ef
Autor:
Tianzhou Ye, Zetao Wang, Yingwei Wu, Jing Zhang, Ping Chen, Mingjun Wang, Wenxi Tian, G. H. Su, Suizheng Qiu
Publikováno v:
Journal of Materials Research. 38:828-840
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::963d39f4f3ee51b61b818a6ae0be2f73
https://doi.org/10.1557/s43578-022-00867-w
https://doi.org/10.1557/s43578-022-00867-w
Publikováno v:
Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology.
Nuclear fuel cladding is subjected to neutron irradiation in a high-temperature stress environment, and the structural integrity of the cladding is very important for the safe operation of nuclear reactors. FeCrAl alloy has become a promising candida
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::86bb1097df5ce47e53b3e46979dda5e8
https://doi.org/10.1115/icone29-89079
https://doi.org/10.1115/icone29-89079
Autor:
Zhou Jiancheng, Guanghui Su, Dalin Zhang, Wenxi Tian, Gongle Song, Jian Deng, Rulei Sun, Suizheng Qiu, Tianzhou Ye
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 1, Pp 61-68 (2021)
Experiments of vertically upward steam-water two-phase flow have been carried out in single-side heated narrow rectangular channel with a gap of 3 mm. Flow patterns were identified and classified through visualization directly. Slug flow was only obs
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::518a7eb3b689558a3652669fd9c509f0
http://www.sciencedirect.com/science/article/pii/S1738573320301960
http://www.sciencedirect.com/science/article/pii/S1738573320301960
Publikováno v:
Materials & Design, Vol 206, Iss, Pp 109766-(2021)
FeCrAl alloys have been proposed as nuclear fuel cladding materials in hope of offering great potential in accident tolerance for light water reactors. However, only a limited amount of data has been published on their creep properties. This work aim
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9665d847ff426e7d8838e5f82a2d8f68
http://www.sciencedirect.com/science/article/pii/S0264127521003191
http://www.sciencedirect.com/science/article/pii/S0264127521003191
Autor:
Jiatong Tan, Quan Li, Bo Zhao, Chao Ma, Yingwei Wu, Yuanming Li, Jing Zhang, Yanan He, Tianzhou Ye, Cheng Zhang, Wenxi Tian, Guanghui Su, Suizheng Qiu
Publikováno v:
Annals of Nuclear Energy. 169:108914
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::72d8cc40247b56d6944047e69a33aab5
https://doi.org/10.1016/j.anucene.2021.108914
https://doi.org/10.1016/j.anucene.2021.108914