Zobrazeno 1 - 10
of 22
pro vyhledávání: '"Laishun Wang"'
Autor:
Laishun Wang, Weijie Ye, Xiaoqiang He, Shuai Wu, Pingjian Ming, Jun Wang, Hui Cheng, Binghuo Yan
Publikováno v:
Applied Thermal Engineering. 204:117968
Comparison of pool boiling CHF of a polished copper block and carbon steel block on a declined slope
Publikováno v:
Journal of Nuclear Science and Technology. 55:1065-1078
This study conducts a critical heat flux (CHF) experiment on a carbon steel block, and the block is positioned on slope that is declined at angles of 5° and 10°. The results of the carbon steel blo...
Publikováno v:
International Journal of Heat and Mass Transfer. 120:300-304
In previous research on nuclear reactors, the effect of irradiation on heat transfer has rarely been studied. We investigated the electron beam irradiation effect on downward-facing flow boiling heat transfer and critical heat flux. All the critical
Publikováno v:
Annals of Nuclear Energy. 113:344-352
The effectiveness of ex-vessel cooling systems in response to severe nuclear reactor accidents is attributable, in part, to the critical heat flux (CHF). As such, CHF enhancement has been the focus of significant research. Prior studies have demonstr
Autor:
B.H. Yan, Laishun Wang
Publikováno v:
Annals of Nuclear Energy. 164:108636
The hydraulic behavior of coolant flow in reactor pressure vessel plays an important role in the thermal hydraulic and safety analysis of nuclear reactor system. Conventional reactor hydraulic tests were carried out by linearly down scaled facilities
Autor:
Laishun Wang, B.H. Yan
Publikováno v:
Annals of Nuclear Energy. 164:108609
Steam generator is one of the key facilities in nuclear power plant. Due to its complex structure and huge volume, the experimental and numerical research of steam generator needs a large amount of costs and computational resources. One feasible meth
Autor:
Laishun Wang, B.H. Yan
Publikováno v:
Annals of Nuclear Energy. 161:108440
Scaling is an important issue in nuclear reactor safety analysis. Due to the safety relevance and cost, it is a big challenge for the scientists to design and construct experimental facilities capable of simulating the performance of nuclear reactor
Publikováno v:
International Journal of Heat and Mass Transfer. 115:138-147
The two-phase flow instability in heated channels is an important phenomenon in industrial facilities. The effect of ocean motions upon the flow instability should be predicted accurately for the heat exchangers in floating platform. The reduced orde
Publikováno v:
Progress in Nuclear Energy. 138:103832
The loss of coolant accident (LOCA), as one of the design basis accidents (DBAs), is a hypothetical accident that is usually considered in the design of nuclear power plant. LOCA is caused by small/large breaks in the reactor primary coolant and pres
Publikováno v:
International Journal of Heat and Mass Transfer. 109:93-102
Ex-vessel cooling is an important concept for ensuring safety in a nuclear power plant. Many researchers have focused on critical heat flux (CHF) enhancement using reactor pressure vessels. Previous studies mainly focused on other types of enhancemen