Validation of the 4C Thermal-Hydraulic Code Against 25 kA Safety Discharge in the ITER Toroidal Field Model Coil (TFMC)

Author

Zanino, R. ; Bonifetto, R. ; Heller, R. ; Richard, L. Savoldi

Author_Institution

Dipt. di Energetica, Politec. di Torino, Torino, Italy

Volume

21

Issue

3

fYear

2011

fDate

6/1/2011 12:00:00 AM

Firstpage

1948

Lastpage

1952

Abstract

The first step of the validation of the recently developed thermal-hydraulic code 4C is presented. We study the transient evolution during a so-called standard 25 kA safety discharge of the International Thermonuclear Experimental Reactor (ITER) Toroidal Field Model Coil (TFMC), tested in 2001-2002 in the TOSKA facility at the Karlsruhe Institute of Technology, Germany. The computed outlet He temperatures from both winding and case cooling channels, as well as the local maximum temperature increase of the structures, are shown to be in good agreement with the measured data.

Keywords

code standards; electrical safety; fusion reactor design; fusion reactor safety; superconducting coils; 4C thermal-hydraulic code; ITER toroidal field model coil; TFMC; TOSKA facility; current 25 kA; international thermonuclear experimental reactor toroidal field model coil; safety discharge; Coils; Cooling; Heat transfer; Heating; Helium; Temperature measurement; Windings; Fusion reactors; simulation; superconducting coils;

fLanguage

English

Journal_Title

Applied Superconductivity, IEEE Transactions on

Publisher

ieee

ISSN

1051-8223

Type

jour

DOI

10.1109/TASC.2010.2089771

Filename

5648385