Title :
Mobile tiles for inertial fusion first wall/blanket
Author :
Sawan, M.E. ; Marriott, E.P. ; Aplin, C.S. ; Snead, L.L.
Author_Institution :
Fusion Technol. Inst., Univ. of Wisconsin-Madison, Madison, WI, USA
Abstract :
A conceptually simple first wall (FW) and blanket design for an inertial fusion system based on utilizing mobile FW tiles is presented. Using these tiles that are periodically removed, annealed, and reinstalled, tritium retention and surface erosion concerns for inertial fusion FW could be mitigated. A conceptual configuration has been developed with consideration for laser beam port accommodation and a simple tile insertion and removal scheme. Tritium self-sufficiency can be achieved with a variety of options. The current preferred design option utilizes liquid Li breeder that serves also as coolant for both the FW tiles and blanket with ferritic steel structural material. Thermal analysis for the carbon fiber composite FW tiles in the HAPL nuclear environment indicates that the maximum temperature will be ~1300°C.
Keywords :
carbon fibres; composite materials; fusion reactor blankets; fusion reactor design; fusion reactor reaction chamber; laser fusion; lithium alloys; steel; tiles; tritium handling; C; FeCJk; HAPL nuclear environment; Li; blanket design; carbon fiber composite FW tiles; conceptual configuration; ferritic steel structural material; inertial fusion first wall; laser beam port accommodation; laser inertial fusion; liquid Li breeder; surface erosion; thermal analysis; tritium retention; Annealing; Heating; Inductors; Laser beams; Laser fusion; Optical design; Power lasers; Steel; Thermal conductivity; Tiles; first wall; inertial fusion; nuclear heating; tiles; tritium breeding;
Conference_Titel :
Fusion Engineering, 2009. SOFE 2009. 23rd IEEE/NPSS Symposium on
Conference_Location :
San Diego, CA
Print_ISBN :
978-1-4244-2635-5
Electronic_ISBN :
978-1-4244-2636-2
DOI :
10.1109/FUSION.2009.5226442
