TECNO FUS

TECNO_FUS is a Programme financed by the Spanish Government (by means of a Consolider Ingenio 2010 grant by MICINN, Ref. CSD2008-0079) and oriented towards the development of technologies associated with the Breeding blanket of future fusion power plants.

Generally speaking the purpose of the breeding blanket is twofold: to extract the energy generated in the power reactor, and to convert Lithium into Tritium. Going into the details of these key component of the Fusion reactor the breeding blanket has to guarantee:

•	The shielding of superconducting coils from the plasma (n,γ) radiation with extreme shield
       factors (< mW cm-3)
•	The extraction and amplification of the fusion power (thermal loads in the first wall MWm-2 
       and volumetric (<MWm-3)
•	Tritium self-sufficientcy, i.e. technology of closed tritium cycle as an intrinsic requirement 
       of the DT fusion reactors.

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 dual coolant Lithium Lead (DCLL) or Modular Double Coolant DRM He/Liquid Metal design (Spanish for "Doble Refrigerante Modular" of He/Pb-15.7Li.

Going into some details it is worthwhile to mention some ongoing tasks:

•	ITMA has started the development of a spanish RAFM (ASTURFER(R)) and 
       CIEMAT is making its characterisation. 
       
•	CEIT has started the development of production routes of ceramic materials based 
       on porous SiC and composite SiCf/SiC, for application as insulating channels inserts 
       (FCI= Flow Channel Inserts). This is based on the concept of regenerative DRM/LiPb.  
       The SiC is the Material of choice for its application due to its excellent  thermal 
       stability, mechanical and chemical characteristics at high temperatures. Its low thermal 
       expansion, good thermal shock resistnce, low corrosion in Pb-15.7Li, low activation and
       good resistance to neutron irradiation make it the correct working material.

Institutional participation

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 (UNAV)
Universidad Pontificia de Comillas (ETSII-COMILLAS)
EHU-Universidad del País Vasco
Instituto Químico de Sarriá (Universidad Ramón Llull)
Instituto Tecnológico de Materiales ITMA (Centro Tecnológico del Acero y Materiales Metálicos at Avilés) together with the Universidad de Oviedo (UNIOVI)
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.

Tasks

Leadership researchers are responsible for the following 9 tasks:

Computational neutronics of DRM He/LiPb box
Integral structural design TM/EM of DRM He/LiPB box
Integral CDF computational capabilities for Liquid Metal and gas channels of the DRM He/LiPb box and auxiliary systems
Production of DRM funtional and structural materials
Design of technologies and plant systems
Breeding blanket diagnostic and CODAC architectures
Safety analysis and environmental impact of DRM He/LiPb system
DEMO plasmae & reactor specifications
Blanket & Systems integration and engineering survey

External links

 TECNO_FUS Project in CEIT website]