Zobrazeno 1 - 10
of 104
pro vyhledávání: '"China Experimental Fast Reactor"'
Publikováno v:
International Journal of Heat and Mass Transfer. 138:496-507
The subchannel code ATHAS-LMR has been improved for analyzing thermal-hydraulics characteristics of flow blockage events in the fuel assembly of a sodium-cooled fast reactor (SFR). Based on the in-depth study of the phenomenon of flow blockage and co
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6be9974b80476af019a0f32edf866966
https://doi.org/10.1016/j.ijheatmasstransfer.2019.04.073
https://doi.org/10.1016/j.ijheatmasstransfer.2019.04.073
Publikováno v:
EPJ Web of Conferences, Vol 247, p 10008 (2021)
China Experimental Fast Reactor (CEFR) is a small size sodium-cooled fast reactor (SFR) with a high neutron leakage core fueled by uranium oxide. The CEFR core with 20 MW(e) power reached its first criticality in July 2010, and several start-up tests
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::f796c38d5cf932bbf83a5ffcb51d1ddc
https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_10008.pdf
https://www.epj-conferences.org/articles/epjconf/pdf/2021/01/epjconf_physor2020_10008.pdf
Autor:
Xingkai Huo, Emil Fridman
Publikováno v:
Annals of Nuclear Energy 148(2020), 107707
The China Experimental Fast Reactor (CEFR) is the first SFR operated in China. The CEFR physical start-up tests, conducted in 2010, included control rod (CR) worth (CRW) measurements by the rod drop method. In this study, the transient simulations of
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b96561e630b16a8c3d0f2c88a5a7fa09
https://www.hzdr.de/publications/Publ-31096-1
https://www.hzdr.de/publications/Publ-31096-1
Autor:
Xiao-liang Chen, Xiao Hu
Publikováno v:
Applied Radiation and Isotopes. 137:167-171
As the first sodium cooled fast reactor in China, China Experimental Fast Reactor (CEFR) has many characteristics, such as high power rating, high neutron flux and high neutron leakage as its hard spectrum. These leakage neutrons can be used to produ
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::b7d0e7fb282d83aa45aa31b678fb9f94
https://doi.org/10.1016/j.apradiso.2018.03.020
https://doi.org/10.1016/j.apradiso.2018.03.020
Autor:
Yu Liang, Jing Chen, Dalin Zhang, Mingjun Wang, Shibao Wang, Suizheng Qiu, Ping Song, Guanghui Su, Wang Xin'an, Yapei Zhang
Publikováno v:
Annals of Nuclear Energy. 113:256-269
Different from the square-arrayed fuel rod bundles in pressurized water reactors, the fuel subassembly for sodium-cooled fast reactors features with wire spacers helically wrapped on the fuel rod. This intricate geometry consequently imposes a signif
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::db4712afebf69a180194d652ad6358d7
https://doi.org/10.1016/j.anucene.2017.11.023
https://doi.org/10.1016/j.anucene.2017.11.023
Publikováno v:
Nuclear Engineering and Design. 383:111424
The pool-type sodium-cooled fast reactor decay heat removal system (DHRS) is an important engineered safety system to ensure the establishment of natural circulation in the case of station blackout (SBO). It is of great significance to study characte
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::89fad6a24fed5a2c438e837edd1ccf08
https://doi.org/10.1016/j.nucengdes.2021.111424
https://doi.org/10.1016/j.nucengdes.2021.111424
Autor:
Jingpin Fu, Jun Yang, Yuhao Zhang, Daogang Lu, Ma Xiangfeng, Yizhe Liu, Jiaxuan Tang, Haiqi Zhao, Jiangtao Liang
Publikováno v:
Annals of Nuclear Energy. 160:108398
One Pump Trip (OPT) may cause asymmetric phenomena in China Experimental Fast Reactor (CEFR) primary system. Not only two loops asymmetric coast-down processes and failure pump backflow, but superposition loss of off-site power (SLOOP) or residual he
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::17b134b87e079eb3a589109332d5dc28
https://doi.org/10.1016/j.anucene.2021.108398
https://doi.org/10.1016/j.anucene.2021.108398
Publikováno v:
Journal of Physics: Conference Series. 1985:012046
Steam generator plays an important role in nuclear power plant, especially in a fast reactor. As a barrier to separate the high temperature sodium and high pressure water/steam, it is important to make sure the safety of the steam generator. For this
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a2bde5444664e4e6a8b29b84478508ed
https://doi.org/10.1088/1742-6596/1985/1/012046
https://doi.org/10.1088/1742-6596/1985/1/012046
Publikováno v:
International Journal of Heat and Mass Transfer. 111:508-519
The half-boundary method (HBM) which reduces the order of partial differential equations, is extended with detailed formula derivations to solve heat transfer problems. The method has a comparable accuracy with analytical solution even when a few nod
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cb04526b2af6307389d01f9397ddaaa1
https://doi.org/10.1016/j.ijheatmasstransfer.2017.03.109
https://doi.org/10.1016/j.ijheatmasstransfer.2017.03.109