A complete loss of coolant accident (LOCA) analysis for the inboard component of ITER CDA

Author

Mogahed, E.A. ; Sawan, M.E. ; Khater, H.Y.

Author_Institution

Fusion Technol. Inst., Wisconsin Univ., Madison, WI, USA

Volume

2

fYear

1993

fDate

11-15 Oct 1993

Firstpage

954

Abstract

A two-dimensional thermal transient analysis, r-θ model, has been performed to study three cases of total LOCA in the inboard components for the ITER CDA design using realistic assumptions. The study shows that the first wall can withstand the surface heat flux without active cooling for an extended period of time longer than the 10 seconds normally assumed for the plasma to continue operation after the onset of LOCA. No melting at the first wall or at the blanket is expected, but the lead at the back of the vacuum vessel reaches the melting point within about two days after the onset of LOCA without active cooling. At this time, the front of the vacuum vessel will reach about 600°C. The temperature of the vacuum vessel will rise above 800°C in a week

Keywords

Tokamak devices; accidents; fusion reactor safety; transient analysis; 2D thermal transient analysis; 600 C; 800 C; ITER CDA; ITER CDA design; LOCA; active cooling; first wall; inboard component; loss of coolant accident; melting point; r-&thetas; model; surface heat flux; vacuum vessel; Accidents; Boundary conditions; Coolants; Cooling; Inductors; Physics; Plasma temperature; Safety; Transient analysis; Vacuum technology;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1993., 15th IEEE/NPSS Symposium on

Conference_Location

Hyannis, MA

Print_ISBN

0-7803-1412-3

Type

conf

DOI

10.1109/FUSION.1993.518483

Filename

518483