DocumentCode :
3171449
Title :
Thermo-structural design of the ARIES-III divertor with organic coolant in subcooled flow boiling
Author :
Hasan, M.Z. ; Najmabadi, F. ; Orient, G.E. ; Reis, E. ; Sharafat, S. ; Sze, D.-K. ; Valenti, M. ; Wong, C.P.C.
Author_Institution :
Inst. of Plasma & Fusion Res., California Univ., Los Angeles, CA, USA
fYear :
1991
fDate :
30 Sep-3 Oct 1991
Firstpage :
346
Abstract :
The thermal-hydraulic and structural design of the ARIES-III divertor plate is presented. The divertor plate is made of small-diameter W-3Re tubes laid along the radial direction and coated with 4 mm of plasma-sprayed tungsten on the plasma-facing side to withstand one hard disruption. The plate is contoured to have the constant heat flux of 5.44 MW/m2 on the entire surface. The total divertor thermal power of 629 MW is removed by the organic coolant HB-40 with the same inlet/exit temperatures (340°C/425°C) as in the first-wall/shield coolant circuit. The principal mode of heat transfer is by subcooled flow boiling. The inlet pressure is 5.34 MPa and the exit pressure is 4.3 MPa, which, by passing through an orifice, is reduced to 1 MPa, equal to the first-wall/shield exit pressure. The total coolant flow rate is 3.35 m3/s and the circulation power is 18 MWe. The maximum plate temperature is 821°C. The safety factor with respect to the critical heat flux is ⩾2, and it is ~3 with respect to the maximum allowable plate temperature. Maximum equivalent total, thermal, and pressure stresses are also given
Keywords :
fusion reactor materials; fusion reactor theory and design; ARIES-III divertor; W; constant heat flux; critical heat flux; equivalent total; first-wall/shield coolant circuit; hard disruption; inlet/exit temperatures; maximum allowable plate temperature; maximum plate temperature; organic coolant; orifice; plasma-sprayed; pressure stresses; radial direction; safety factor; small-diameter W-3Re tubes; structural design; subcooled flow boiling; thermal-hydraulic; total coolant flow rate; Atomic measurements; Coolants; Equations; Fusion reactor design; Heat transfer; Inductors; Plasma temperature; Safety; Thermal stresses; Tokamaks;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Fusion Engineering, 1991. Proceedings., 14th IEEE/NPSS Symposium on
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-0132-3
Type :
conf
DOI :
10.1109/FUSION.1991.218807
Filename :
218807
Link To Document :
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