Title :
A simplified torus module for use within an integrated dynamic fusion fuel cycle tritium model for ITER
Author :
Kuan, W. ; Federici, G. ; Gierszewski, P. ; Sugihara, M.
Author_Institution :
MAE Dept., California Univ., Los Angeles, CA, USA
Abstract :
A simplified torus module is developed and tested for inclusion within the integrated tritium fuel cycle dynamic model CFTSIM. It is being applied to simulate the fuel cycle of the International Thermonuclear Experimental Reactor (ITER). The latest T-retention material database is considered and most dominant processes that affect the tritium inventory inside the ITER torus are included at an appropriate level of complexity. Validation against current tokamak data and extrapolation to ITER is discussed. Tritium inventories for various reference ITER operational scenarios are then calculated and discussed
Keywords :
Tokamak devices; fusion reactor fuel; fusion reactor materials; fusion reactor operation; nuclear engineering computing; tritium; CFTSIM; ITER; International Thermonuclear Experimental Reactor; T; T-retention material database; fuel cycle; integrated dynamic fusion fuel cycle tritium model; integrated tritium fuel cycle dynamic model; operational scenarios; simplified torus module; tokamak data; tritium inventory; Databases; Extrapolation; Feeds; Fuels; Inductors; Plasma density; Plasma properties; Plasma temperature; Testing; Tokamaks;
Conference_Titel :
Fusion Engineering, 1997. 17th IEEE/NPSS Symposium
Conference_Location :
San Diego, CA
Print_ISBN :
0-7803-4226-7
DOI :
10.1109/FUSION.1997.687048
