Design and analyses of nuclear components require a wide set of competencies in different domains and the handling of several numerical tools. A 3D model of the component to be analysed has to be built via CAD tools (i.e. CATIA) and imported in the computational tool used for the numerical analyses. Fluid dynamic, thermal and mechanical analyses are performed by means of Finite Volume and Finite Elements Codes. The main tool used in the group is the commercial code ANSYS. As the development of complex designs requires more and more a multi physic approach, the group is involved in developing and implementing in ANSYS sophisticated sub-models developed in other codes (i.e. ABAQUS for the structural material, STAR CD or CFX for the fluid dynamic analyses). An expertise exists in mechanical design qualification and assessment of the components (licensing of nuclear components) by means of the design Codes and Standards (i.e. ASME, RCC-MR).
The DAF team is strongly involved in the frame of the Test Blanket Module design development activities for ITER. KIT is responsible for the Design of the Helium Cooled Pebble Bed Test Blanket Module (HCPB TBM). A complete set of design studies have been realised in the last three years for the conceptual design of the HCPB TBM: from the identification of the loading scenario, the fluid dynamic analyses, the validation of the thermal design, the steady state and transient thermo mechanical analyses up to the qualification with respect the selected codes and standard. An intense technical collaboration has been carried on in the frame of this project with Budapest University of Technology in Hungary and with CEA Saclay in France. Other major project is the design and integration of In-Vessel Components for the DEMO reactor conceptual studies. DEMO Blanket designs based on the HCPB concept are proposed along with the integration and maintenance strategy. After a review work performed during the last two years, a new design phase of the DEMO In Vessel components is starting based on direct interaction with other fields (plasma physics, divertor development etc.)
|HCPB TBM CAD 3D model with view of the internal structure, temperature field after 40s during a typical ITER pulse (transient analyses of a ¼ scaled HCPB FE model) and deformed shape of the HCPB TBM after 40s from the beginning of the plasma pulse (transient analyses of a ¼ scaled HCPB FE model)|