Pioro I L,Duffey R B.Heat transfer and hydraulic resistance at supercritical pressures in power engineering applications[M].New York:ASME Press,2007:175-181.
[2]
Oka Y.Review of high temperature water and steam cooled reactor concepts[C]//Proceeding of SCR-2000.Tokyo,Japan,2000:37-57.
[3]
Schulenberg T,Starflinger J.Core design concepts for high performance light water reactors[J].Nuclear Engineering and Technology,2007,39(4):249-256.
[4]
Cheng X,Kuang B,Yang Y H.Numerical analysis of heat transfer in supercritical water cooled flow channels[J].Nuclear Engineering and Design,2007,237(3):240-252.
[5]
Yamagata K,Nishikawa K,Hasegawa S,et al.Forced convective heat transfer to supercritical water flowing in tubes[J].International Journal of Heat and Mass Transfer,1972,15(12):2575-2593.
[6]
Shitsman M E.Impairment of the heat transmission at supercritical pressures[J].High Temperature,1963,1(2):237-244.
[7]
Wang Weishu,Bi Qincheng,Gu Hongfang,et al.An investigation on heat transfer to water flowing in vertical upward internally ribbed enhancement tube at supercritical pressure[J].Advanced Science Letters,2011,4(6-7):2281-2288.
[8]
Wang Jianguo,Li Huixiong,Guo Bin,et al.Investigation of forced convection heat transfer of supercritical pressure water in a vertically upward internally ribbed tube[J].Nuclear Engineering and Design,2009,239(10):1956-1964.
[9]
Zhu Xiaojing,Bi Qincheng,Yang Dong,et al.An investigation on heat transfer characteristics of different pressure steam-water in vertical upward tube[J].Nuclear Engineering and Design,2009,239(2):381-388.
Wu Gang,Bi Qincheng,Wang Han,et al.Experimental investigation of heat transfer for supercritical pressure water flowing in inclined upward tube[J].Journal of Xi’an Jiaotong University,2011,45(5):6-11(in Chinese).
Cai Hong,Wu Yanhua,Yang Dong.Experimental investigation on heat transfer characteristics of low mass-flux optimized rifled tube[J].Proceedings of the CSEE,2011,31(26):65-70(in Chinese).
[14]
Ackerman J W.Pseudo-boiling heat transfer to supercritical pressure water in smooth and ribbed tubes[J].Journal of Heat Transfer,Transactions of the ASME,1970,92(3):490-498.
[15]
Sakurai K,Ko H S,Okamoto K,et al.Visualization study for presdo-boiling in supercritical carbon dioxide under forced convection in rectangular channel[C]//Proceeding of SCR-2000.Tokyo,Japan,2000:180-184.
[16]
Jiang P X,Zhao C R,Shi R F,et al.Experimental and numerical study of convection heat transfer of CO 2 at super-critical pressures during cooling in small vertical tube[J].International Journal of Heat and Mass Transfer,2009,52(21-22):4748-4756.
[17]
王建国.超临界锅炉水冷壁管低质量流速下的传热及阻力特性研究[D].西安:西安交通大学,2010.
[18]
Wang Jianguo.Investigation on heat transfer and frictional pressure drop at low mass flux in the water-wall tubes of supercritical boiler[D].Xi’an:Xi’an Jiaotong University,2010(in Chinese).
[19]
Griem H.Untersuchungen zur thermohydraulik innenberippter verdampferrohre[D].München,Germany:Technische Universitat München,1995.
[20]
Pioro I L,Khartabill H F,Duffey R B.Heat transfer to supercritical fluids flowing in channels-empirical correlations(survey)[J].Nuclear Engineering and Design,2004,230(1-3):69-91.
[21]
Yang Xingbo,Su G H,Tian Wenxi,et al.Numerical study on flow and heat transfer characteristics in the rod bundle channels under super critical pressure condition[J].Annals of Nuclear Energy,2010,37(12):1723-1734.
[22]
Wang Weishu,Zhang Hongsheng,Bi Qincheng,Liu Jun.Numerical study on the heat transfer characteristics of supercritical water in enhanced sub-channels in reactors[J].Advanced Materials Research,2010,156-157(10):426-431.
[23]
Gu Hanyang,Yu Yiqi,Cheng Xu,et al.Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels[J].Nuclear Science and Techniques,2008,19(3):178-186.
[24]
Li Hongzhi,Wang Haijun,Luo Yushan,et al.Experimental investigation on heat transfer from a heated rod with a helically wrapped wire inside a square vertical channel to water at supercritical pressures[J].Nuclear Engineering and Design,2009,239(10):2004-2012.
[25]
Wu Gang,Bi Qincheng,Yang Zhendong,et al.Experimental investigation of heat transfer for supercritical pressure water flowing in vertical annular channels[J].Nuclear Engineering and Design,2011,241(9):4045-4054.
[26]
Wang Han,Bi Qincheng,Yang Zhendong,et al.Experimental and numerical study on the enhanced effect of spiral spacer to heat transfer of supercritical pressure water in vertical annular channels[J].Applied Thermal Engineering,2012,48(15):436-445.