Prime pagine RA2010FUS:Copia di Layout 1 - ENEA - Fusione
Prime pagine RA2010FUS:Copia di Layout 1 - ENEA - Fusione
Prime pagine RA2010FUS:Copia di Layout 1 - ENEA - Fusione
Create successful ePaper yourself
Turn your PDF publications into a flip-book with our unique Google optimized e-Paper software.
progress report<br />
2010<br />
003<br />
038 JET Collaboration<br />
039 Pellet stu<strong>di</strong>es<br />
039 High beta operation<br />
040 Dust<br />
040 L to H mode transition<br />
040 Safety factor profile determination<br />
041 Upgrade of neutron profile monitor (KN3N)<br />
041 Elaboration of JET programme for 2011<br />
041 Coor<strong>di</strong>nation of other Italian partners<br />
042 Plasma control<br />
042 References<br />
046 Fusion Advanced Stu<strong>di</strong>es Torus<br />
046 Introduction<br />
047 Physics<br />
047 Transport simulations<br />
048 Energetic particle physics in H–mode scenario with combined NNBI and ICRH<br />
049 Plasma–Wall interaction activities and optimization of the <strong>di</strong>vertor geometry<br />
049 Diagnostics<br />
050 Design Description<br />
050 Divertor design<br />
051 First wall design<br />
052 Vacuum vessel design<br />
052 Toroidal field coil system<br />
053 Toroidal field ripple reduction<br />
053 Poloidal field coil system<br />
054 Poloidal field coil system flexibility and plasma control<br />
054 Cooling system<br />
054 Remote handling<br />
055 References<br />
056 Technology Programme<br />
056 Introduction<br />
057 Divertor, First Wall, Vacuum Vessel and Shield<br />
057 Manufacturing technology for the ITER inner vertical target<br />
057 Qualification of ultrasonic non–destructrive testing method for plasma facing<br />
components<br />
058 Analysis of the ITER <strong>di</strong>vertor cassettes<br />
060 Breeder Blanket and Fuel Cycle<br />
060 European Bree<strong>di</strong>ng Blanket Test Facility design and construction<br />
060 TRIEX loop for studying technologies of tritium extraction from Pb–17Li<br />
060 Electromagnetic load analysis for the design of the blanket manifold pipe<br />
concept for ITER<br />
061 Development of method for highly tritiated water handling in ITER tritium plant<br />
061 Training activities<br />
062 Magnet and Power Supply