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

Volume

1

fYear

1997

fDate

6-10 Oct 1997

Firstpage

325

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;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1997. 17th IEEE/NPSS Symposium

Conference_Location

San Diego, CA

Print_ISBN

0-7803-4226-7

Type

conf

DOI

10.1109/FUSION.1997.687048

Filename

687048