首页|Thermal hydraulic analysis on the heat transfer enhancement of the COOL blanket first wall for CFETR
Thermal hydraulic analysis on the heat transfer enhancement of the COOL blanket first wall for CFETR
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NETL
NSTL
Elsevier
The supercritical CO2 cOoled Lithium-Lead (COOL) blanket is one of the advanced candidate blankets for China Fusion Engineering Test Reactor (CFETR). In this blanket, the first wall (FW) is subjected to high heat flux from plasma and the nuclear heat produced by the interaction between the blanket materials and neutrons. To ensure that the FW has superior heat removal capability and that the material temperature remains below the allowable limit. First of all, this paper conducts the thermal- hydraulic optimization in view of the hydraulic diameter and pitch to achieve a better smooth channel design. Then, the effects of two heat transfer enhancement techniques, i. e. artificial roughness and placement of ribs (both set on the wall close to the plasma side of the front wall), on the maximum temperature of the FW are analyzed. Considering both pressure drop and heat transfer, the enhanced heat transfer performance is evaluated using PEC. The results show that setting a roughness of 0.045 mm at the fillet and coupling V-shaped ribs with the distance of 25 mm and an angle of 60 degrees on the front wall can reduce the maximum temperature of FW from the original 551 degrees C to 508 degrees C, achieve a convective heat transfer coefficient (HTC) of 9290 W/(K & sdot;m2), and attain PEC of 1.85. Finally, stress evaluation of this design is performed using ANSYS Mechanical, and the results meet the design specification standards.
NETL
NSTL
Elsevier
