TECNO FUS

TECNO-FUS is a Programme financed by the Spanish Government (by means of a Consolider grant by MICINN, Ref. CSD2008-079) and oriented towards the development of technologies associated with the breeding blanket of future fusion power plants.

The purpose of the breeding blanket is twofold: to extract the energy generated in the power reactor, and to convert Lithium into Tritium.

Associated techniques involve neutron detection, the development of materials (Eurofer steel, ceramics, SiC or composite SiCf/SiC), the management of liquid metals in strong magnetic fields, and thermomechanical calculations in complex geometries. The first design of a dual coolant, dual functionality model is not original of TECNO-FUS, what is original is the development of the so called DRM design (Spanish for "Doble Refrigerante Modular").

Institutions involved are specialized Centres and Universities all over Spain, e.g.

• Centro de Estudios e Investigaciones Técnicas de Gipuzkoa (CEIT) of the Universidad de Navarra (UDEN)
• Universidad Pontificia de Comillas (ETSII-COMILLAS)
• EHU-Universidad del País Vasco
• Instituto Químico de Sarriá (Universidad Ramón Llull)
• ITMA (at Llanera-Avilés)
• Universidad Complutense de Madrid
• UNED
• Universidad Politécnica de Cataluña
• Universidad Politécnica de Madrid

The work is coordinated by CIEMAT, acting as Management Entity, such that the Head of the LNF is also the Research Coordinator. The project includes a Technical Secretary.

Leadership researchers are responsible for the following 9 tasks:

• Computational neutronics of DRM He/LiPb box (Task 1)
• Integral structural design TM/EM of DERM He/LiPB box (Task 2)
• Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He LiPb box and auxiliary systems (Task 3)
• Production of DRM funtional and structural materials (Task 4)
• Design of technologies and plant systems (Task 5)
• Breeding blanket diagnostic and CODAC architectures (Task 6)
• Safety analysis and environmental impact of DRM He/LiPb system (Task 7)
• DEMO plasmae & reactor specifications (Task 8)
• Blanket & Systems integration and engineering survey (Task 9)