Design and thermal-hydraulic analysis of tokamak divertor armor tiles
- North Carolina State Univ., Raleigh, NC (United States). Dept. of Nuclear Engineering
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/m{sup 2} and a transient disruption load of 140 MJ/m{sup 2} over 100 {micro}s 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 1,760 K and 4,800 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.
- OSTI ID:
- 505837
- Report Number(s):
- CONF-950905-; ISBN 0-7803-2970-8; TRN: 97:013530
- Resource Relation:
- Conference: 16. IEEE/NPSS symposium on fusion engineering, Champaign, IL (United States), 1-5 Oct 1995; Other Information: PBD: 1995; Related Information: Is Part Of 1995 IEEE 16. symposium on fusion engineering. Volume 1; Miley, G.H.; Elliott, C. [eds.] [Univ. of Illinois, Urbana, IL (United States). Fusion Studies Lab.]; PB: 886 p.
- Country of Publication:
- United States
- Language:
- English
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