Zobrazeno 1 - 10
of 51
pro vyhledávání: '"Jia Dounan"'
Publikováno v:
In Progress in Nuclear Energy 2011 53(1):1-9
Publikováno v:
In Nuclear Science and Techniques 2007 18(4):247-251
Publikováno v:
In Nuclear Science and Techniques 2007 18(3):186-192
Publikováno v:
In Annals of Nuclear Energy 2007 34(4):288-296
Publikováno v:
In Nuclear Engineering and Design 2003 225(2):219-247
Publikováno v:
Nuclear Engineering and Design. 237:2175-2182
Experimental study associated with CHF and dryout point in narrow annuli is conducted with 1.5 mm and 1.0 mm gap, respectively. Distilled water is used as work fluid. The parameters examined were: pressure from 2.0 MPa to 4.0 MPa; mass flux from 26.0
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a26c726bfc9fdfd14a9ff3e966338532
https://doi.org/10.1016/j.nucengdes.2007.03.043
https://doi.org/10.1016/j.nucengdes.2007.03.043
Publikováno v:
Frontiers of Energy and Power Engineering in China. 1:174-180
The molten salt reactor (MSR), which is one of the generation IV reactors, can meet the demand of transmutation and breeding. The thermodynamic properties of the molten salt system like LiF-NaF-BeF2 influence the design and construction of the fuel s
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a6ae4c99c17202070bc7f0a9ee06710c
https://doi.org/10.1007/s11708-007-0022-x
https://doi.org/10.1007/s11708-007-0022-x
Publikováno v:
Frontiers of Energy and Power Engineering in China. 1:189-194
A multi-channel model steady-state thermal-hydraulic analysis code was developed for the China Advanced Research Reactor (CARR). By simulating the whole reactor core, the detailed mass flow distribution in the core was obtained. The result shows that
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::34a0297b0d29c7dc83cfd3093389ad5a
https://doi.org/10.1007/s00000-007-0024-8
https://doi.org/10.1007/s00000-007-0024-8
Publikováno v:
Nuclear Engineering and Design. 235:1737-1747
Experimental study associated with two-phase flow and heat transfer during flow boiling in two vertical narrow annuli has been conducted. The parameters examined were: mass flux from 38.8 to 163.1 kg/m 2 s; heat flux from 4.9 to 50.7 kW/m 2 for insid
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::23e4ec5f0e9546f9e739a2db26e9a1e3
https://doi.org/10.1016/j.nucengdes.2005.03.002
https://doi.org/10.1016/j.nucengdes.2005.03.002
Publikováno v:
Nuclear Engineering and Design. 225:305-313
TMI and Chernobyl accidents, having pronounced impact on nuclear industries, triggered the governments as well as interested institutions to devote much attention to the safety of nuclear power plant and public’s requirements on nuclear power plant
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2601bbd7ff03c4ae974d42d26b1729b3
https://doi.org/10.1016/s0029-5493(03)00178-x
https://doi.org/10.1016/s0029-5493(03)00178-x