Study and thermal-hydraulic design of water cooled PFC for SST-1 tokamak

Author

Chaudhuri, P. ; Reddy, D. Chenna ; Khirwadkar, S. ; Prakash, N. Ravi ; Santra, P. ; Saxena, Y.C.

Author_Institution

Inst. for Plasma Res., Gandhinagar, India

fYear

2002

fDate

2002

Firstpage

422

Lastpage

425

Abstract

The plasma facing components (PFCs) are an important part of Steady State Superconducting Tokamak (SST-1) design. PFC of SST-1 consists of divertors, passive stabilizers, baffles and limiters are designed to be compatible for steady state operation. The main consideration in the design of the PFC is the steady state heat removal of up to 1 MW/m². During steady-state operation, the average heat loads on divertor and passive stabilizers are expected to be 0.6 and 0.25 MW/m² respectively. The PFC has been design to withstand the peak heat fluxes and also without significant erosion such that frequent replacement is not necessary. Design considerations included 2-D steady state and transient tile temperature distribution and resulting thermal loads in PFC during cooling. Coolant parameters necessary to maintain optimum thermal-hydraulic design, tile surface temperature, and tile fitting mechanism. A 2-D finite difference code has been developed to study of flow behavior and thermal response of PFC during cooling.

Keywords

Tokamak devices; finite difference methods; fusion reactor design; fusion reactor divertors; fusion reactor limiters; fusion reactor operation; nuclear engineering computing; temperature distribution; SST-1 tokamak; Steady State Superconducting Tokamak; average heat loads; baffles; divertors; finite difference code; fusion reactors; limiters; optimum thermal-hydraulic design; passive stabilizers; peak heat fluxes; plasma facing components; steady state operation; thermal-hydraulic design; tile fitting mechanism; tile surface temperature; transient tile temperature distribution; water cooled PFC; Coolants; Cooling; Finite difference methods; Plasma temperature; Steady-state; Surface fitting; Temperature distribution; Thermal loading; Tiles; Tokamaks;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 2002. 19th Symposium on

Print_ISBN

0-7803-7073-2

Type

conf

DOI

10.1109/FUSION.2002.1027727

Filename

1027727