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Design study of ITER-like divertor target for DEMO
- Source :
- Fusion Engineering and Design
- Publication Year :
- 2015
- Publisher :
- Elsevier Ltd, 2015.
-
Abstract
- A near-term water-cooled target solution has to be evaluated together with the required technologies and its power exhaust limit under 'DEMO' conditions. The ITER-like design concept based on the mono-block technology using W as armour material and the CuCrZr-IG as structural material with an interlayer of pure copper represents a promising solution also for DEMO. This work reports the design study of an "optimized" ITER-like Water Cooled Divertor able to withstand a heat flux of 10 MW m-2, as requested for DEMO operating conditions. The optimization of plasma facing unit (PFU) aims to enhance the thermo-mechanical behaviour of the component by varying some geometrical parameters (monoblock size, interlayer thickness and, tube diameter and thickness). The optimization was performed by means of the multi-variable optimization algorithms using the FEM code ANSYS. The coolant hydraulic conditions (inlet pressure, temperature and velocity) were fixed for simplicity. This study is based on elastic analysis and 3 dimensional modelling. The resulting optimized geometry was evaluated on the basis of the ITER SDC-IC criteria and in terms of low cycle fatigue (LCF). The margin to the critical heat flux (CHF) was also estimated. Further design study (taking into account the effect of neutron radiation on the material properties) together with mock-up fabrication and high-heat-flux (HHF) tests are foreseen in next work programmes. © 2015 Elsevier B.V. All rights reserved.
- Subjects :
- Demo divertor
Work (thermodynamics)
ITER SDC-IC criteria
Materials science
Structural material
Critical heat flux
Mechanical Engineering
Nuclear engineering
Divertor
Critical heat flux (CHF)
ANSYS code
High heat flux (HHF)
Finite element method
Coolant
Nuclear Energy and Engineering
Heat flux
General Materials Science
Material properties
Civil and Structural Engineering
Subjects
Details
- Language :
- English
- Database :
- OpenAIRE
- Journal :
- Fusion Engineering and Design
- Accession number :
- edsair.doi.dedup.....eddf38b732790ca5e887c7954bf223ff