Title :
Design and thermal-hydraulic analysis of tokamak divertor armor tiles
Author :
Sharpe, J.P. ; Carter, T.A. ; Bourham, M.A. ; Gilligan, J.G.
Author_Institution :
Dept. of Nucl. Eng., North Carolina State Univ., Raleigh, NC, USA
fDate :
30 Sep-5 Oct 1995
Abstract :
A prototype divertor armor tile design has been investigated using water-cooled ATJ graphite tiles fitted to a copper heat sink. Two-dimensional steady-state and 1-D time dependent heat transfer codes were developed to determine thermal design characteristics. A steady-state heat flux of 5 MW/m2 and a transient disruption load of 140 MJ/m2 over 100 μs were assumed for an ITER-type device operating in a radiative divertor configuration. For a tile fitted to the heat sink by a bonded-pin mechanism, the optimal armor thickness was determined to be 1.0 cm, with a 2.2 cm diameter coolant channel. The maximum steady state and disruption temperatures of the tile were determined to be 1760 K and 4800 K, respectively. LOCA analysis yielded that a 7 second response time would be needed after loss-of-coolant in the armor tile. The design is predicted to survive approximately 6 disruptions before tile replacement would be necessary
Keywords :
Tokamak devices; copper; fusion reactor design; fusion reactor materials; fusion reactor safety; graphite; 1760 to 4800 K; LOCA analysis; bonded-pin mechanism; copper heat sink; loss-of-coolant; radiative divertor configuration; steady-state heat transfer code; thermal-hydraulic analysis; time dependent heat transfer code; tokamak divertor armor tiles; transient disruption load; water-cooled ATJ graphite tiles; Bonding; Coolants; Copper; Heat sinks; Heat transfer; Prototypes; Steady-state; Tiles; Tokamaks; Water heating;
Conference_Titel :
Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium
Conference_Location :
Champaign, IL
Print_ISBN :
0-7803-2969-4
DOI :
10.1109/FUSION.1995.534198