Abstract
The target box is designed to protect the body of divertor cassette. Every new EAST divertor cassette has two target boxes covering its body. The paper is about the structure design and optimizing scheme of the outer/inner tokamak divertor target box. The preliminary structure of target box is built up firstly. And the distribution of thermal load on the target boxes is discussed based on the theory and experiment results of plasma. Then some parameters of the target box’s structure, such as cooling tube radius, cooling water flow velocity and the length between two cooling tube, are selected to discuss the range of values’ limits. Based on the above results, a series of thermal simulations are made through changing the structure parameter values. Finally, using these simulation results the optimal design parameters set are found out.
This is a preview of subscription content, log in via an institution to check access.
Similar content being viewed by others
References
Y.T. Song, D.M. Yao et al., Thermal and mechanical analysis of the EAST plasma facing components. Fusion Eng. Des. 75–79, 499–503 (2005)
L. Wang, G.S. Xu et al., Particle and power deposition on divertor targets in EAST H-mode plasmas. Nucl. Fusion 52, 063024 (2012)
L. Cao, Z. Zhou, D. Yao, EAST full tungsten divertor design. J. Fusion. Energ. 34, 1451–1456 (2015)
Y.M. Duan, L.Q. Hu et al., Radiation distribution and energy loss during ELM in EAST. J. Nucl. Mater. 438, s338–s341 (2013)
Y.P. Chen, J.Y. Wang et al., Modelling studies of SOL-divertor plasmas in EAST tokamak with high heating and current driving power. J. Nucl. Mater. 415, S517–S522 (2011)
P.C. Stangeby, G.M. McCracken, Plasma boundary phenomena in tokamaks. Nucl. Fusion 30(7), 1225 (1990)
C. Giroud, G. Maddison et al., Integration of a radiative divertor for heat load control into JET high triangularity ELMy H-mode plasmas. Nucl. Fusion 52, 063022 (2012)
T.K. Gray, R. Maingi et al., Dependence of divertor heat flux widths on heating power, flux expansion, and plasma current in the NSTX. J. Nucl. Mater. 415, S360–S364 (2011)
Z. Jing, Measurement and analysis of the radiated power for the ohmic discharges in the J-TEXT tokamak [D] 2012.5 (in Chinese)
G.M. McCracken, U. Samm, Studies of heating and impurity transport in the plasma boundary of tokamaks. AIP Conf. Proc. 257, 144 (1992)
W. Jun, Experimental study on basic performance for divertor plasmas in the EAST tokamak [D] (Institute of Plasma Physics, Chinese Academy of Sciences, Beijing, 2009), p. 5
W. Suttrop et al., Plasma Phys. Control. Fusion 40, 771 (1998)
D.N. Hill, A review of ELMs in divertor tokamaks. J. Nucl. Mater. 241–243, 182–198 (1997)
A.W. Leonard, A. Herrmann et al., The impact of ELMs on the ITER divertor. J. Nucl. Mater. 266–269, 109–117 (1999)
Summary of material properties for structural analysis of the ITER internal components ITER_D_23HL7T v.3.2
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
About this article
Cite this article
Liang, C., Zhang, Y., Cao, L. et al. Preliminary Design and Optimization of the Multilayer Alloy Divertor Target Box. J Fusion Energ 35, 859–863 (2016). https://doi.org/10.1007/s10894-016-0112-z
Published:
Issue Date:
DOI: https://doi.org/10.1007/s10894-016-0112-z