A simplified torus module for use within an integrated dynamic fusion fuel cycle tritium model for ITER

摘要

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.