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steel - 4 10 10 Zircaloy - 4 10 ~ 5-8 3000 - 16000 0.2 CuCrZr & CFC/W Coolant - pressure MPa - temperature °C - velocity m/s - leak rate g/s Water-Steam 28 280-600 3 <50 Water 15 285-325 5 <50(SG) Water 4 100 – 150 9 – 11 <10-7 Comparisons Slide 59 ITER International Summer School 2009 Thermo-Hydraulics Coolant Flow Path Divertor coolant design parameters Inlet temperature: 100 °C Inlet water pressure: 4.2 MPa Total pressure drop: < 1.4 MPa CHF margin: > 1.4 Total flow rate: < 1000 kg/s Slide 60 ITER International Summer School 2009 Pressure drop vs.flow rate have been measured on Outer and Inner Vertical target and Dome (ENEA Brasimone) Hydraulic testing of DOME Hydraulic testing of IVT Experiments Thermo-Hydraulics Slide 61 ITER International Summer School 2009 Critical Heat Flux Slide 62 ITER International Summer School 2009 Terminology, Flat Tile and Monoblock Slide 63 ITER International Summer School 2009 M M FT FT Slide 64 ITER International Summer School 2009 Vertical Target Medium-Scale Prototype • W macrobrush: 15 MW/m2 x 1000 cycles • CFC monoblock 20 MW/m2 x 2000 cycles • CHF test > 30 MW/m2 Test results Slide 65 ITER International Summer School 2009 • W monoblocks: 10 MW/m2 x 1000 cycles • CFC monoblock 10 MW/m2 x 1000 cycles 20 MW/m2 x 1000 cycles 23 MW/m2 x 1000 cycles Vertical Target Full-Scale Prototype Slide 66 ITER International Summer School 2009 1995 2002 1998 Slide 67 ITER International Summer School 2009 Vertical Target component with W armour Tested in FE200 facility (50°C-12 m/s – 3.3MPa) 5 MW/m2 x 100 cycles 10 MW/m2 x 1000 cycles 20 MW/m2 x 1000 cycles Slide 68 ITER International Summer School 2009 Vertical Target Medium Scale Prototype by Hot Radial Pressing The testing of medium-scale vertical target prototype manufactured by HRP-Hot Radial Pressing at ENEA Frascati in the FE200 facility (CEA-Areva) 3000 cycles at 10 MW/m2 2000 cycles
Download scientific diagram | The design of the fusion reactor ITER and Standard Sun Model from publication: Nuclear fusion problems | We will burn coal,
Millions of components will be integrated in the biggest fusion device. The assembly of the device will be one of the most complex engineering operations.
ITER is the first integrated fusion test reactor. It is a joint international research and development project that aims to
The purpose of this document is to present some considerations on the safety and radiation protection issues that should be examined from the design stage of “
Table 9.6-1 Summary of ITER Cost Estimates Cost (kIUA) Construction costs Direct capital cost 2755 Management and support 477 R&D during construction 60-80 Operation costs (average/year) Permanent personnel 60 Energy ~ 30 Fuel ~ 8 Maintenance/improvements ~ 90 Total 188 Decommissioning cost 335 ITER G A0 FDR 4 01-09-10 R 0.6 Summary of the ITER Final Design Report Page 80 10 Conclusions The ITER project has its origins in the common recognition by the world’s leading fusion programmes world-wide of : • the potential of fusion as a practical long-term energy source, with acceptable environmental characteristics • the need for the next step on the path towards realising fusion energy to be the construction and operation of a burning plasma experiment allowing, in one device, full exploration of the physics issues as well as proof of principle, testing of key technological features of possible fusion power stations and demonstration of their safety and environmental characteristics, and • the attractions of preparing to take such a step in an international collaborative framework which would allow participants to share costs and pool scientific and technological expertise towards a common goal.
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