Title :
A fusion chamber design with a liquid first wall and divertor
Author :
Nygren, R.E. ; Sze, D.-K. ; Nelson, B.E. ; Fogarty, P.J. ; Eberle, C. ; Rognlien, T.D. ; Rensink, M.E. ; Smolentsev, S. ; Youssef, M.Z. ; Sawan, M.E. ; Merrill, B.J. ; Majesk, R.
Author_Institution :
Sandia Nat. Labs., Albuquerque, NM, USA
Abstract :
The APEX study is investigating the use of free flowing liquid surfaces to form the inner surface of the chamber around a fusion plasma. We present a design for the chamber of a 3840 MW fusion reactor based on the configuration for the chamber and magnets from ARIES-RS but with a fast flowing molten salt of mixed Be, Li and Na fluorides for the first wall and divertor and molten salt blanket with a ferritic steel structure. Our design analysis includes strong radiation from the core and edge plasma, (liquid) MHD effects on the weakly conducting molten salt, a recycling first wall stream that enables a high efficiency thermal conversion, and evaluations of breeding, neutronics, tritium recovery and safety.
Keywords :
Tokamak devices; fusion reactor blankets; fusion reactor design; fusion reactor divertors; magnetohydrodynamics; plasma toroidal confinement; plasma-wall interactions; 3840 MW; APEX; ARIES-RS; MHD effects; breeding; divertor; fast flowing molten salt; ferritic steel structure; free flowing liquid surfaces; fusion chamber design; fusion plasma; fusion reactor; high efficiency thermal conversion; inner surface; liquid first wall; magnets; molten salt blanket; neutronics; plasma core; plasma edge; recycling first wall stream; safety; tritium recovery; weakly conducting molten salt; Fusion reactor design; Fusion reactors; Magnetic analysis; Magnetic cores; Magnetohydrodynamics; Magnets; Plasmas; Recycling; Steel; Thermal conductivity;
Conference_Titel :
Fusion Engineering, 2003. 20th IEEE/NPSS Symposium on
Print_ISBN :
0-7803-7908-X
DOI :
10.1109/FUSION.2003.1426641
