Title :
Structural analyses and preliminary design of HT-7U cryostat
Author :
Yu, J. ; Wu, S.T. ; Song, Y.T. ; Weng, P.D.
Author_Institution :
Inst. of Plasma Phys., Chinese Acad. of Sci., Hefei, China
Abstract :
The cryostat of HT-7U Tokamak is a large vacuum vessel surrounding the entire Basic Machine with cylindrical shell, dished top and flat bottom. The main function of HT-7U cryostat provides the thermal barrier between the ambient temperature testing hall and the liquid helium cooled superconducting magnet. The loads applied to the cryostat are vacuum pressure, dead weight, seismic events and electromagnetic forces originated by eddy currents. It also provides feed through penetrations for all the connecting elements inside and outside the cryostat. The main material selected for the cryostat is stainless steel 304L. The structural analyses including buckling for the cryostat vessel under the plasma operation condition have been carried out using a finite element code. Stress analysis results show that the maximum stress intensity was below the allowable value. In this paper, we emphasize on the structural analyses of HT-7U cryostat. The preliminary design of the cryostat is also described.
Keywords :
Tokamak devices; buckling; cryostats; finite element analysis; fusion reactor design; fusion reactor materials; nuclear engineering computing; plasma toroidal confinement; stainless steel; stress corrosion cracking; superconducting magnets; thermal stress cracking; vacuum apparatus; 304L; HT-7U cryostat design; ambient temperature testing hall; buckling; cylindrical shell; dead weight; dished top; eddy currents; electromagnetic forces; finite element code; flat bottom; large vacuum vessel; liquid helium cooled superconducting magnet; maximum stress intensity; plasma operation condition; seismic events; stainless steel; stress analysis; structural analyses; thermal barrier; vacuum pressure; Eddy currents; Electromagnetic forces; Feeds; Helium; Joining processes; Plasma temperature; Stress; Superconducting magnets; Testing; Tokamaks;
Conference_Titel :
Fusion Engineering, 2002. 19th Symposium on
Print_ISBN :
0-7803-7073-2
DOI :
10.1109/FUSION.2002.1027715