Zobrazeno 1 - 10
of 60
pro vyhledávání: '"Bingde Chen"'
Publikováno v:
International Journal of Photoenergy, Vol 2018 (2018)
An experimental investigation of phase distribution for subcooled flow boiling in an inclined circular tube (i.d. 24 mm) was conducted in this paper. The local interfacial parameters were measured by a double-sensor optical fiber probe, and the measu
Externí odkaz:
https://doaj.org/article/7f4bfaaf9ced45b1bc2d272bce5b6161
Autor:
Zejun, Xiao, Xianhui, Song, Xuemei, Lang, Xuesong, Bai, Jieliang, Ma, Pengfei, Wang, Bingde, Chen
Publikováno v:
In Nuclear Engineering and Design 2004 229(2):213-222
Publikováno v:
In Nuclear Engineering and Design 2003 225(2):305-313
Publikováno v:
Annals of Nuclear Energy. 78:26-32
A coupled three dimensional neutronics/thermal-hydraulics code STTA (SCWR Three dimensional Transient Analysis code) is developed for SCWR core transient analysis. Nodal Green’s Function Method based on the second boundary condition (NGFMN_K) is us
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::251d9cc8dc5339418ae795d7b948151f
https://doi.org/10.1016/j.anucene.2014.12.025
https://doi.org/10.1016/j.anucene.2014.12.025
Publikováno v:
Nuclear Engineering and Design. 260:11-15
UO 2 high burnup structure has an important impact on fuel behavior, especially in case of reactivity initiated accident (RIA). Pore relaxation enhances local fuel swelling and puts additional load to the fuel cladding, which makes fuel more suscepti
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5f3186a29688415bc25fccfb8c625822
https://doi.org/10.1016/j.nucengdes.2013.03.028
https://doi.org/10.1016/j.nucengdes.2013.03.028
Publikováno v:
Nuclear Engineering and Design. 257:61-66
An in-core fuel management code package for uranium zirconium hydride power reactor, which is developed on the basis of the assembly lattice code TPFAP and the core calculating code BMFGD for LWR, is firstly introduced in this paper. The inherent saf
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6fab323a45486d25e1a1f6c49c8044d2
https://doi.org/10.1016/j.nucengdes.2013.01.017
https://doi.org/10.1016/j.nucengdes.2013.01.017
Publikováno v:
Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors.
Plenum temperature is an important parameter in the calculation of LWR fuel rod internal pressure, since plenum contributes over 40% of free volume in typical LWR fuel design. In many fuel performance codes the plenum temperature are determined in a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::140a68dc08f6d5011d6c7a6cf3730909
https://doi.org/10.1115/icone24-60330
https://doi.org/10.1115/icone24-60330
Publikováno v:
Nuclear Engineering and Design. 240:3851-3861
Natural circulation is one of the most important thermal-hydraulic phenomena that makes the fluid flow along a closed loop without any external driving force. With this merit, it is adopted by the passive heat removal system to bring the residual hea
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::0aec85456bd1efbcea7eb65d9e12017f
https://doi.org/10.1016/j.nucengdes.2010.08.012
https://doi.org/10.1016/j.nucengdes.2010.08.012
Publikováno v:
Annals of Nuclear Energy. 37:691-700
For some Pressurized Water Reactors (PWR) operated on automobiles, boats or deep sea vessels, natural circulation simulation is important for understanding their safety during severe accidents, or system characteristics when natural circulation is ad
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::44f62ddff48df0841f5ae41eb32d0ec9
https://doi.org/10.1016/j.anucene.2010.02.002
https://doi.org/10.1016/j.anucene.2010.02.002
Publikováno v:
Frontiers of Energy and Power Engineering in China. 2:524-527
The pressure pulse filter and Smagorinsky subgrid stress model of the Large Eddy Simulation (LES) are introduced. The fluid field in the annular plenum between the pressure vessel and the core barrel of the1:5 model in the second phase of Qinshan Nuc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f9c2d26fc28007df081a5fbf4ebf9713
https://doi.org/10.1007/s11708-008-0099-x
https://doi.org/10.1007/s11708-008-0099-x