A high performance water-cooled thermal shield device

Author

Pizzuto, A. ; Sangiovanni, C.

Author_Institution

Centro Ricerche Energia Frascati, ENEA sulla Fusion, Rome, Italy

Volume

2

fYear

1993

fDate

11-15 Oct 1993

Firstpage

855

Abstract

The shielding of the heat flux coming from plasma is one of the most limiting factors in plasma-facing component (PFC) design. In fact, the performance of a cooled divertor plate system is mainly limited by the heat transfer capability (maximum value of the critical heat flux CHF) and by the capability to sustain thermal stresses, even if the maximum allowable heat flux is determined by the thermal conductivity of the protective material (maximum temperature value on the plasma facing surface). A new concept for cooled thermal shield design was devised and tested. Analyses and tests demonstrate that the new concept introduces very high improvement in PFC design, in terms of both heat removal capability (very high CHF) and related stress performance. Up to 80 MW/m ² under steady state were successfully applied

Keywords

fusion reactor design; fusion reactors; shielding; thermal stresses; critical heat flux; design; fusion reactor; heat removal; heat shield; plasma-facing component; thermal shield; thermal stress; water-cooled; Conducting materials; Heat transfer; Performance analysis; Plasma devices; Plasma materials processing; Plasma temperature; Protection; Testing; Thermal conductivity; Thermal stresses;

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.1993.518459

Filename

518459