Design and thermal-hydraulic analysis of PFC baking for SST-1 Tokamak

Citation
P. Chaudhuri et al., Design and thermal-hydraulic analysis of PFC baking for SST-1 Tokamak, FUSION ENG, 55(4), 2001, pp. 521-534
Citations number
16
Categorie Soggetti
Nuclear Emgineering
Journal title
FUSION ENGINEERING AND DESIGN
ISSN journal
09203796 → ACNP
Volume
55
Issue
4
Year of publication
2001
Pages
521 - 534
Database
ISI
SICI code
0920-3796(200109)55:4<521:DATAOP>2.0.ZU;2-E
Abstract
The Steady-State Superconducting Tokamak (SST-1) is a medium-size tokamak w ith super-conducting magnetic field coils. Plasma facing components (PFC) o f the SST-1, consisting of divertors, passive stabilisers, baffles, and pol oidal limiters, are designed to be compatible for steady-state operation. E xcept for the poloidal limiters, all other PFC are structurally continuous in the toroidal direction. As SST-1 is designed to run double-null divertor plasmas, these components also have up-down symmetry. A closed divertor co nfiguration is chosen to produce high recycling and high pumping speed in t he divertor region. The passive stabilisers are located close to the plasma to provide stability against the vertical instability of the elongated pla sma. The main consideration in the design of the PFC is the steady-state he at removal of up to 1 MW/m(2). In addition to removing high heat fluxes, th e PFC are also designed to be compatible for baking at 350 degreesC. Differ ent flow parameters and various tube layouts have been examined to select t he optimum thermal-hydraulic parameters and tube layout for different PFC o f SST-1. Thermal response of the PFC during baking has been performed analy tically (using a Fortran code) and two-dimensional finite element analysis using ANSYS. The detailed thermal hydraulics and thermal responses of PFC b aking is presented in this paper. (C) 2001 Elsevier Science B.V. All rights reserved.