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Title: Thermal and hydraulic analysis of a cylindrical blanket module design for a tokamak reactor

Technical Report ·
DOI:https://doi.org/10.2172/5723602· OSTI ID:5723602

Various existing blanket design concepts for a tokamak fusion reactor were evaluated and assessed. These included the demonstration power reactors of ORNL, GA and others. As a result of this study, a cylindrical, modularized blanket design concept was developed. The module is a double-walled, stainless steel 316 cylinder containing liquid lithium for tritium breeding and is cooled by pressurized helium. Steady state and transient thermal conditions under normal and some off-design conditions were analyzed and presented. At the steady state reference operating point the maximum structure temperature is 452/sup 0/C at the maximum stressed location and is 495/sup 0/C at the less stressed location. The coolant inlet pressure is 54.4 atm, the inlet temperature is 200/sup 0/C and the exit temperature is 435/sup 0/C. The coolant could be utilized with a helium/steam turbine power conversion system with a cycle thermal efficiency of 30.8%.

Research Organization:
Westinghouse Electric Corp., Pittsburgh, PA (USA). Fusion Power Systems Dept.
DOE Contract Number:
W-7405-ENG-26
OSTI ID:
5723602
Report Number(s):
WFPS-TME-78-103
Country of Publication:
United States
Language:
English