EU-WORKSHOP FUSION PROGRAMME ROADMAP FOR FP8 IPP- GARCHING BULGARIAN EURATOM – INRNE FUSION ASSOCIATION INSTITUTE FOR NUCLEAR RESEARCH AND NUCLEAR ENERGY (INRNE) INSTITUTE FOR SOLID STATE PHYSICS (ISSP), INSTITUTE FOR ELECTRONICS (IE), SOFIA UNIVERSITY (SU) AND TECHNICAL UNIVERSITY – SOFIA Experience of the research institutions in the following areas: Investigations on mechanisms and diagnostics of negative ion beam sources. Development of volume-production based RF sources of negative hydrogen ions. Defect structure studies in fusion neutrons irradiated materials- Model predictions of accumulated defects in the irradiated fusion materials. Improving the resolution of Thomson scattering LIDARs by application of novel deconvolution – based algorithms” Spectroscopic study of the transport of tungsten atoms and ions near the wall. Energy and particle confinement/ transport: Langmuir probe measurements of the plasma potential and EEDF for edge turbulence diagnostics at COMPASS tokamak. Numerical investigations on selected problems associated with the development of power gyrotrons. Investigation of vortex-glass-vortex-liquid phase transition in over doped polycrystalline Y1-xCaxBa2Cu3O7-δ samples. Neutronics calculations in support of the design (activation, heating, shielding, T breeding and damage) of the test blanket modules for ITER.

EU-WORKSHOP FUSION PROGRAMME ROADMAP FOR FP8 IPP- GARCHING EURATOM-INRNE ASSOCIATION Priority task for FP FP FP Development of plasma auxiliary systems 2.1. Heating and current drive systems Development of volume-production based RF sources of negative hydrogen ions with ion production in the plasma volume, since such a source – a volume-production based rf source – is considered as the most proper solution. As the decision for ITER is for a two-chamber surface- production based rf source (with cesium). Coordination of the work with UKEA and CEA Cadarache is expected where ideas for inductively-driven – by planar coils – sources are also under development.

EU-WORKSHOP FUSION PROGRAMME ROADMAP FOR FP8 IPP- GARCHING Development of plasma auxiliary systems The studies (both theoretical and experimental ones) up to now have been carried out in parallel on two types of inductively driven rf sources: the tandem two-chamber plasma source, the concept of the ITER source. The work directed towards understanding the mechanisms governing the operation of the tandem two-chamber source. The source has been constructed based on an idea for locality (elementary processes), its operation is governed by non-locality (transport processes). The modification of the rf ITER source to a two-chamber source, with plasma expansion from the driver to the second – larger size – chamber, results into strong drop of the electron density in the second chamber, where the extraction is located, which could not ensure efficient volume production of the ions.

EU-WORKSHOP FUSION PROGRAMME ROADMAP FOR FP8 IPP- GARCHING First wall Vacuum Vessel (VV) Plasma Facing Components Divertor Breeding Blanket Components and Materials near the Fusion Plasma Blanket Shielding Blankets in ITER, water cooled Breeding Blankets in DEMO, He cooled Divertor Water cooled in ITER He-cooled in DEMO Plasma Facing Materials: C, Be, W Structural Materials Stainless steel 316L-IG in ITER Ferritic Steels (EUROFER, ODS materials) in DEMO W-alloys for He cooled divertor

EU-WORKSHOP FUSION PROGRAMME ROADMAP FOR FP8 IPP- GARCHING EURATOM – INRNE ASSOCIATION Priority task for FP FP FP8+2 Defects Structure Studies in Neutron Irradiated fusion materials: Positron Lifetime Model Calculations Collaboration: CU.Slovakia, SCK-CEN, CEA. 1.Positron lifetime model calculations of perfect Be, W, α-Fe or Fe-Cr lattice. 2.Calculation of PLT for monovacancy, divacancy, empty nanovoids and nanovoids containing H and He atoms in 14 Mev neutron Irradiated fusion materials.

EU-WORKSHOP FUSION PROGRAMME ROADMAP FOR FP8 IPP- GARCHING EURATOM-INRNE ASSOCIATION Priority task for FP FP FP8+2 Improving the resolution of Thomson scattering LIDARs by application of novel deconvolution–based algorithms. Improved software packet for analysis of JET core Lidar data with an impact on the determination of the true pedestal characteristics. parameters. Simulation analysis of the novel method for determination of the electron temperature pedestal from jet core lidar data. Processed Thomson-scattering LIDAR (KE3) data from JET measurement campaigns. Evaluation of statistical parameters (resolution, pedestal, ingredients, etc.) of retrieved electron temperature and density profiles (convolved and deconvolved). Theoretical analysis and results on the distortion effect of a relatively long (with respect to the fusion plasma variation scales) TS lidar pulse response on the recovered profiles of the electron temperature and concentration.

EU-WORKSHOP FUSION PROGRAMME ROADMAP FOR FP8 IPP- GARCHING Estimation of the AC losses in the wires and tapes of YBCO materials with different level of Ca substitution. In collaboration with: Leibniz Institute for Solid State and Materials Research, Dresden, Germany, Prof. Dr. G. Fuchs, Institute of Low Temperature and Structure Research, Polish Academy of Sciences, Wroclaw, Poland, Prof. Dr. A. Zaleski 1. Investigation the AC losses of Ag- sheathed monofilament wires and tapes. 2. The technology for manufacturing of the monofilament tapes and tapes shall be optimized for better performance and for reducing the AC losses at different magnetic fields. Investigations of polycrystalline YBCO samples with different grain size show some morphology dependence of z establishing the larger z values for the samples with smaller grain size.

EU-WORKSHOP FUSION PROGRAMME ROADMAP FOR FP8 IPP- GARCHING

PALS (Positron annihilation lifetime spectroscopy) provides essential quantitative information on defects in materials at atomistic, nanoscopic and microscopic levels with high very high spatial resolution.

EU-WORKSHOP FUSION PROGRAMME ROADMAP FOR FP8 IPP- GARCHING EURATOM-INRNE ASSOCIATION Priority task for FP FP FP8+2 Components and Materials near the Fusion Plasma Blanket Shielding Blankets in ITER, water cooled Breeding Blankets in DEMO, He cooled Divertor Water cooled in ITER He-cooled in DEMO Plasma Facing Materials: C, Be, W Structural Materials Stainless steel 316L-IG in ITER Ferritic Steels (EUROFER, ODS materials) in DEMO W-alloys for He cooled divertor

EU-WORKSHOP FUSION PROGRAMME ROADMAP FOR FP8 IPP- GARCHING