Experimental research on heat transfer enhancement for high Prandtl-number fluid

被引:23
作者
Chiba, SY [1 ]
Omae, M
Yuki, K
Hashizume, H
Toda, S
Sagara, A
机构
[1] Tohoku Univ, Grad Sch Eng, Sendai, Miyagi 980, Japan
[2] DENSO Corp, Kariya, Aichi, Japan
[3] Tohoku Radiol Sci Ctr, Sendai, Miyagi, Japan
[4] Natl Inst Fus Sci, Gifu, Japan
关键词
D O I
10.13182/FST05-A746
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 [核科学与技术]; 082701 [核能科学与工程];
摘要
The experimental research on heat-transfer enhancement for such high Prandtl-number fluid as Flibe has been performed with a large molten salt circulating experimental loop named as "TNT loop" (Tohoku-NIFS Thermofluid loop). Through the experiments, a packed-bed tube is employed as the enhanced for molten salt. It is clarified that the enhancement of packed-bed tube is superior to that of turbulent heat transfer from the viewpoint of the same flow rate. Also, the 1/4-diameter bed is superior to the 1/2-diameter one at the same flow rate. Furthermore, at low flow rate, a little differences of heat transfer performance can be seen between the stainless-steel bed and copper bed. At high flow rate, however, the heat-transfer coefficient ratio strongly depends on the flow rate in the case of the 1/4-diameter copper bed only. As a result, it is considered that the thermal energy is expanded from a heated wall deeply and fast through packed bed at low flow rate. On the contrary, it is also considered that the convective heat transfer in the vicinity of a heated wall is strong at high flow rate. The evaluation from the viewpoint of the pressure drop shows that the turbulent heat transfer is superior to that with packed bed However, the ratio of heat transfer with bed to turbulent one is steeply improved at low flow rate. Taking account of MHD effect, avoidance of erosion and electrolysis of Flibe, the enhancement under low flow-rate condition can be suitable in a fusion reactor.
引用
收藏
页码:569 / 573
页数:5
相关论文
共 10 条
[1]
Heat transfer enhancement for a molten salt FLiBe channel [J].
Chiba, S ;
Toda, S ;
Yuki, K ;
Sagara, A .
FUSION TECHNOLOGY, 2001, 39 (02) :779-783
[2]
CHIBA S, IN PRESS NUMERICAL R
[3]
Cooke J.W., 1973, Technical Report ORNL-TM-4079
[4]
EBARA S, 1998, P 11 INT HEAT TRANSF, V4, P503
[5]
ERGUN S, 1952, CHEM ENG PROG, V48, P89
[6]
Numerical investigation of forced convection heat transfer in porous media using a thermal non-equilibrium model [J].
Jiang, PX ;
Ren, ZP .
INTERNATIONAL JOURNAL OF HEAT AND FLUID FLOW, 2001, 22 (01) :102-110
[7]
BLANKET AND DIVERTOR DESIGN FOR FORCE-FREE HELICAL REACTOR (FFHR) [J].
SAGARA, A ;
MOTOJIMA, O ;
WATANABE, K ;
IMAGAWA, S ;
YAMANISHI, H ;
MITARAI, O ;
SATOW, T ;
TIKARAISHI, H .
FUSION ENGINEERING AND DESIGN, 1995, 29 :51-56
[8]
Experimental research on molten salt thermofluid technology using a high-temperature molten salt loop applied for a fusion reactor Flibe blanket [J].
Toda, S ;
Chiba, S ;
Yuki, K ;
Omae, M ;
Sagara, A .
FUSION ENGINEERING AND DESIGN, 2002, 63-64 :405-409
[9]
[10]
Heat transfer by forced convection in pipes packed with porous media whose matrices are composed of spheres [J].
Varahasamy, M ;
Fand, RM .
INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER, 1996, 39 (18) :3931-3947