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
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
