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FinnFusion Coordinator


Association Euratom-Tekes (1995-2013)

Fusion Physics Programme under EFDA and CoA

The Association concentrates on work in a limited number of areas, where existing expertise shall be developed to establish centres of excellence. Fusion physics work covers plasma theory/modelling, plasma-wall interactions and diagnostics. The major part of the Finnish programme is integrated in the EFDA and JET work programmes. 

The research topics include edge plasmas and plasma-wall interactions, transport, advanced tokamak scenarios and diagnostics. The main tokamak experiments for Tekes Association are Joint European Torus (JET) in UK and ASDEX Upgrade (AUG) in Germany.

Code development is an essential element in the Tekes programme to support EFDA Task Force Integrated Tokamak Modelling (ITM). Domestic codes include the particle following Monte Carlo code ASCOT and gyrokinetic transport code ELMFIRE. ASCOT is widely used to model JET and AUG plasmas and recently for modelling of ripple losses in ITER. A gyrokinetic transport code ELMFIRE is under benchmarking and further development, but has already produced interesting results for small tokamaks.

Ion beam and SIMS (Secondary Ion Mass Spectroscopy) facilities has been used for plasma-wall interaction studies such as erosion, re-deposition, hydrogen retention and mobility of the plasma facing materials. Tungsten coated divertor tiles and "smart tiles" for diagnostics have been provided and installed to JET and AUG. The tiles will be later analysed to study e.g., the material transport and erosion/re-deposition rates. Molecular dynamic simulations and ERO code (originated from FZJ Jülich) are used to model plasma-wall interactions.

Workprogramme of Association Euratom-Tekes for 2011-2013:

  • Edge/SOL physics with plasma-wall interactions and material transport in the SOL region including erosion and re-deposition studies, deuterium-tritium retention, material transport, T-inventory in plasma facing materials, tritium cleaning and modelling of edge plasmas and plasma-wall interactions.

  • Transport phenomena including modelling of advanced tokamak and baseline scenarios, internal transport barriers, hybrid scenarios, momentum transport and real time control, integrated predictive transport modelling of the JET ELMy H-mode plasmas and MHD modelling of ELMs for JET.

  • NPA (Neutral Particle Analyser) diagnostics upgrade for JET and NPA simulations for AUG.

  • MEMS magnetometer diagnostics development will continue as a F4E Grant.

  • Development of particle codes including gyrokinetics (ELMFIRE, ASCOT).

  • Goal Oriented Training, GOTiT (theory and modelling) and GOTRH (remote handling.

In addition, Tekes provides two Deputy Task Force Leaders at JET, scientific co-ordinators for predictive and interpretative modelling and data analysis of JET and AUG experiments, secondees to CCFE JOC team and a member in the HLST (high level support team) for HPC-FF (high performance computing).

The main topics of the Estonian Research Unit are:

  • Tritium depth profile measurements of samples from JET by accelerator based mass-spectrometry for plasma-wall interaction studies.

  • Laboratory tests to demonstrate that laser induced plasma spectroscopy (LIPS) can be applied for the first wall erosion diagnostics will be performed. The aim of the experiment is to use LIPS for online erosion diagnostics in the future.

Emerging Technology under EFDA

A major fraction of the Tekes technology R&D is ITER related and will go under the new Joint Undertaking F4E. Regarding the so called emerging technologies under EFDA, the emphasis is in

  • Materials research related modelling and experiments on radiation effects in Tungsten, Tungsten alloys and ODS steels.

EFDA remote handling (RH) activities are related to the Goal Oriented Training Programme, in which TUT IHA is the co-ordinator in GOTRH and to JET RH operations for the installation of the ITER-like-Wall by JOC secondee from Tekes Association.

Fusion Technology for ITER

Tekes Associate has a high expertise in remote handling (RH) related technologies such as water hydraulics and virtual reality modelling of RH tools and operations. At the moment, the major fraction of the VTT and TUT IHA RH resources are directed to the F4E Grant work or ITER Tasks.

  • Divertor Test Platform for ITER (DTP2) at VTT

  • Development of waterhydraulic maipulators for ITER maintenance at TUT

  • New manufacturing methods (i.e., powder HIP) for vacuum vessel, shield and first wall structures (VTT, Industry)

  • Advavced welding methods and welding/cutting robots at LUT