Design of Cooling Water System (CWS) for CRAFT Lower Hybrid ‎Current Driven (LHCD) System‎

Document Type : Research Paper

Authors

1 Institute of Plasma Physics, Chinese Academy of Sciences, No. 350 Shushanhu Road, Hefei, 230031, Anhui, China

2 University of Science and Technology of China, No. 96 Jinzhai Road, Hefei, 230026, Anhui, China

3 Anhui Jianzhu University, No. 856 Jinzhai South Road, Hefei, 230022, Anhui, China‎

Abstract

Lower hybrid current driven (LHCD) system, as the most efficient non-inductive current drive method in the tokamak, is an integral part of the Comprehensive Research Facility for Fusion Technology (CRAFT). The cooling water system (CWS) is necessary to be designed to remove the thermal power generated by the clients of the LHCD system so that system could operate safely. Therefore, a thermal hydraulic model is developed by AFT Fathom aimed at investigating thermal hydraulic behavior of the system under the normal operation. According to the calculation results, the CWS can provide required pressure, temperature and flow rate to address the client requirements of LHCD system. The study could provide a design reference for the construction of cooling water system for LHCD system and other CRAFT subsystems.

Keywords

Main Subjects

[1] Bin G, Giovanni D, O, Teodoros L, Ployhar S, Jun T, Peng F, Lei Y Ajith K, Dinesh G, Nirav P and Mahesh J, Thermal-Hydraulic Analysis of ITER Component Cooling Water System Loop 2B, Journal of Fusion Energy, 35(2), 2015, 335-340.
[2] Bin G, Zhiquan S, Peng Fu, Xuesong X, Chuan L, Min W and Lin D, Design of coolant distribution system (CDS) for ITER PF AC/DC convertor, Fusion Engineering and Design, 108, 2016, 21-27.
[3] Wei Z, Bin G, Jie Z and G.Dell O, Hydraulic analysis on ITER component cooling water system 2B, Fusion Engineering and Design, 121, 2017, 204-210.
[4] P.A., Di Maio, S. Garitta, J.H. You, G. Mazzone and E. Vallone, Thermal-hydraulic optimization of the DEMO divertor cassette body cooling circuit equipped with a liner, Fusion Engineering and Design, 146, 2019, 220-223.
[5] Francesco Edemetti, Emanuela Martelli, Alessandro Tassone, Gianfranco Caruso and Alessandro Del Nevo, DEMO WCLL breeding zone cooling system design: Analysis and discussion, Fusion Engineering and Design, 146, 2019, 2632-2638.
[6] Shijun Q, Yang Z, Tiejun X, Lei C, Kun L, Zhuang X, Damao Y, Shengming W, Yuntao S, RAMI analysis for EAST upper full tungsten divertor cooling system, Fusion Engineering and Design, 124, 2017, 1181-1186.
[7] G.Dell O and Ancona A, Steady state and transient thermal-hydraulic analyses on ITER divertor module, Fusion Engineering and Design, Fusion Engineering and Design, 75, 2005, 457-461.
[8] Rene A and Merola M, Overview of the design and R&D of the ITER blanket system, Fusion Engineering and Design, 87, 2012, 769-776.
[9] Zanino R, Bonifetto R, Cau F, Portone A and Savoldi R L, CFD analysis of the ITER first wall 06 panel. Part II: Thermal-Hydraulics, Fusion Engineering and Design, 89, 2014, 431-441.
[10] Applied Flow Technology, AFT Fathom User’s Guide, 2008.
[11] Qingyuan M, Jiping G., Fluid mechanics and distribution network, Metallurgical Industry Press, Beijing, 2010.
[12] Chuan H., Lijun G., Pump and Fans, China Electric Power Press, Beijing, 2008.