1. 2 nd EU-US DCLL Workshop University of California, Los Angeles, Nov. 14-15 th, 2014

2. A project-oriented structure set-up Resources in Horizon 2020 secured A new governance system based on the principle of joint programming Federici

3. ITER will show scientific/engineering feasibility: –Plasma (Confinement/Burn, CD/Steady State, Disruption control, edge control) –Plasma Support Systems (LTSC magnets, fuelling, H&CD systems) Most components inside the ITER VV are not DEMO relevant, e.g., materials, design. TBM provides important information, but limited scope. Still a divergence of opinions on how to bridge the gaps to fusion power plants Most of the issues are common to any next major facility after ITER DEMO Issues/gaps For any further step, safety, power exhaust, breeding, RH and plant availability are important design driver and CANNOT be compromised T breeding blanket technology (M4) Divertor design configuration and technology (M2 & M6) Safety and licensing (M5) Plant design integration incl. BoP (M6) Operating plasma scenario and control and efficient CD systems (M1) Remote maintenance and plant availability (M6) Federici

4. Develop a feasible and integrated DEMO blanket system conceptual design of 4 concepts. BoP cycle and technology plays a substantial role in concept selection. Complementarity with TBM Programme Federici

5. Bocaccini

7. Activities started only a few months ago and a significant effort has been put on defining the basis of the project

8. US IB DCLL blanket design Long (~10 M) poloidal banana-shape segments to match the vertical maintenance scheme PbLi Tin/Tout=350°C/ 450°C to avoid corrosion problems The poloidal flow velocity is 0.38 m/s The sandwich-type (steel-alumina steel) FCI as electrical insulator. He Tin/Tout=350°C/ 450°C The magnetic field used in the analysis is 10 T Smolentsev, Malang

9. Full parametric Catia model  easy and fast modifications. Poloidal ducts with rectangular cross section. Turns in planes perpendicular to the toroidal magnetic field. The module is toroidally divided into 4 parallel PbLi circuits. Stiffening grid radial walls. Internal helium manifolds Back Supporting Structure:  Integration of service connections for every modules.  Shielding & supporting functions.  Helium  feeding to internal manifolds for distribution. 1800 mm BZ 680 mm 2140 mm 1300 mm 300 mm 910 mm Breeding Zone BSS He PbLi FW Rapisarda

10. Safety MHD Tritium, including extraction FCI development (either sandwich or SiC) and characterization More experimental data are needed!!! Reviewed available and future facilities, but more work is needed in this area Carloni Mas, Smolentsev, Munipalli Utili, Ying, Moreno, Humrickhouse Norajita, Katoh, Gonzalez Fernandez, Morley, Callis, Merrill

11. Corrosion: do we understand? Coatings (for corrosion and/or permeation): do we have a reliable coating technology? Can we built a DCLL without coatings? ….

12. Can we speed up the DCLL develoment in order to compite with the other alternatives in 5 years time? EU-US collaboration!!! (to increase the critical size of the team and reduce learning curve) Sucessful workshop (I hope we will be able to show in the near future)

13. Yes!!!! I think it would be useful Proposal: Linked (before or after) to the next SOFT Conference (Prague, September 2016), or ISFNT12 (Jeju Island, Korea, September 2015) To be soon agreed