Engineering design and thermal hydraulics of plasma facing components of SST-1
Description
SST-1 is a medium size tokamak with super conducting magnetic field coils. All the subsystems of SST-1 are designed for quasi steady state (∼1000 s) operation. Plasma Facing Components (PFCs) of SST-1 consisting of divertors, passive stabilizers, baffles and poloidal limiters are also designed to be compatible for steady state operation. As SST-1 is designed to run double null divertor plasmas, these components also have up-down symmetry. A closed divertor configuration is chosen to produce high recycling and high pumping speed in the divertor region. All the PFC are made of copper alloys (CuCrZr and CuZr) on which graphite tiles are mechanically attached. These copper alloy back plates are actively cooled with water flowing in the channels grooved on them with the main consideration in the design of PFCs as the steady state heat removal of about 1.0 MW/m2. In addition to be able to remove high heat fluxes, the PFCs are also designed to be compatible for baking at 350 degree sign C. Extensive studies, involving different flow parameters and various cooling layouts, have been done to select the final cooling parameters and layout. Thermal response of the PFCs and vacuum vessel during baking, has been calculated using a FORTRAN code and a 2-D finite element analysis. The PFCs and their supports are also designed to withstand large electro-magnetic forces. Finite element analysis using ANSYS software package is used in this and other PFCs design. The engineering design including thermal hydraulics for cooling and baking of all the PFCs is completed. Poloidal limiters are being fabricated. The remaining PFCs, viz. divertors, stabilizers and baffles are likely to go for fabrication in the next few months. The detailed engineering design, the finite element calculations in the structural and thermal designs are presented in this paper
Additional details
Identifiers
- PII
- S0920379601005889;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 56-57
- Journal Issue
- 4
- Journal Page Range
- p. 355-362
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 33035188
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Descriptors DEI
- A CODES; BAFFLES; COPPER ALLOYS; DESIGN; DIVERTORS; FINITE ELEMENT METHOD; FIRST WALL; GRAPHITE; HEAT FLUX; HYDRAULIC EQUIPMENT; LIMITERS; STEADY-STATE CONDITIONS; SUPERCONDUCTING COILS; THERMONUCLEAR REACTOR COOLING SYSTEMS; TOKAMAK DEVICES
- Descriptors DEC
- ALLOYS; CALCULATION METHODS; CARBON; CLOSED PLASMA DEVICES; COMPUTER CODES; CONTROL EQUIPMENT; COOLING SYSTEMS; ELECTRIC COILS; ELECTRICAL EQUIPMENT; ELEMENTS; ENERGY SYSTEMS; EQUIPMENT; FLOW REGULATORS; MINERALS; NONMETALS; NUMERICAL SOLUTION; THERMONUCLEAR DEVICES; THERMONUCLEAR REACTOR WALLS; TRANSITION ELEMENT ALLOYS
Optional Information
- Copyright
- Copyright (c) 2001 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.