VTT TECHNICAL RESEARCH CENTRE OF FINLAND
LTD
Fusion research activities in
Finland and VTT
Serpent Workshop, Cambridge UK
J. Leppänen and M. Airila
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Overview
FinnFusion Consortium
Academy
of Finland
Linked third parties: Aalto,
HY, LUT, TUT, ÅA
VTT
TEM
Program owner/
Tekes
Fusion for Energy
F4E / ITER
Industry
National Advisory Board
Consortium Steering
Group
Program manager/
VTT
EUROfusion Consortium / IPP
Euratom/Commission
Organigram of Finnish Fusion Research Community in 2015-2020
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Fusion technology
research in Finland –
DTP2
Edge plasma physics and plasma-wall
interactions are our focus area since
2004
Background in
Simulations of energetic particles, transport and RF heating
Simulations of plasma-material interaction and materials modifications
Experimental plasma-wall interaction research
How it all started
 Edge and PWI modelling identified as the link between existing
expertises
 Collaboration with FZ Jülich from 2004: Simulations with and
development of the ERO code
Presently about 20 active scientists (graduate, post-doc, senior)
E.g. PSI 2014 conference: 45 contributions, 4 orals (out of 60)
6/16/15
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ASCOT code for 2D/3D tracing of
fast plasma ions
“Accelerated
Simulation of Charged
particle Orbits in Tori”
 ITER contract:
 Simulation of fusion alphas, neutral
beam ions, RF heated ions
 will they destroy the wall?
 Limiters receive the highest loads and
protect the wall elsewhere
 Assessing critical design issues  High
reliability requirements for model
 Several PhD theses completed on ASCOT
related topics during the past year
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Edge and SOL plasma modelling
L. Aho-Mantila, M. Groth, A. Järvinen, J. Karhunen, D. Moulton
JET experiments and interpretation with EDGE2D-EIRENE
 Interpretation of N and Ne seeding experiments in JET-ILW
 Radiation and detachment physics in JET-C and JET-ILW
 Neutral dynamics and pumping including subdivertor
ASDEX Upgrade experiments and interpretation with SOLPS
 Measurements of scrape-off layer flows at the HFS midplane
Development of DEMO power exhaust scenarios within the Power
Plant Physics and Technology Programme
 JET and ASDEX Upgrade experiments at high radiated power, SOLPS
validation and scaling laws
6/16/15
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Impurity migration modelling
L. Aho-Mantila, M. Airila, C. Björkas, M. Groth, A. Järvinen, A. Hakola, T. Makkonen, J. Miettunen
Tools:
 3D Monte Carlo impurity transport code ERO
 ASCOT – recently extended to global impurity tracing in
realistic geometries
 2D impurity transport code DIVIMP
 Plasma codes for plasma background generation
Case examples:
 10Be, 13C and 15N tracer experiments (JET + AUG)
 AUG SOL flow measurement by carbon injection
 Erosion probes exposed to AUG plasmas
Significant efforts also in ERO code developments
 MD data, BeD, ITM work, plasma background handling,
synthetic diagnostics and geometry
6/16/15
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Experimental plasma-wall interaction studies
A. Hakola, K. Heinola, J. Karhunen, J. Likonen, J. Räisänen
Tools:
 SIMS facilities at VTT and University of Helsinki
 Beryllium handling facility at VTT
 Ion-beam analysis (RBS, NRA, ERDA) laboratory at
University of Helsinki
 Access to different microscopes (optical, SEM, TEM,
AFM) at VTT and Aalto University
Case examples:
 In situ monitoring of deposition and retention
 Long-term and tracer samples (JET + AUG)
 Erosion probes exposed to AUG plasmas
 Dust investigations at JET in view of ITER
 Arc-discharge and plasma cleaning
6/16/15
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Multi-scale modelling of plasma-wall interactions
K. Nordlund, T. Ahlgren, M. Airila, C. Björkas, L. Bukonte, K. Heinola, A. Lasa, E. Safi
Long traditions in top-level research at UH
 Increasing integration into the EFDAEUROfusion programme during past ~5 years
 Academy of Finland project ”SimITER” in 20102013 boosted domestic networking (Aalto, UH,
ÅA, VTT & CSC)
 Networking with FZJ, CCFE, IPP, MEdC (incl.
Staff Mobility & JOC Secondment)
6/16/15
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Plasma-wall interactions
and edge plasma
studies
Divertor Test Platform DTP2
• VTT and TUT are hosting the
DTP2 facility since 2007
• Crucial facility for testing and
training remote handling
operations for ITER
• More recently also analyses for
remote handling of DEMO
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Starting activities in
neutronics
Coupling Fusion neutron and 3D neutron transport
models – Overview
 Time scales of transients are affected by the thermal inertia of cooled
components that receive neutron (and decay) heat
 It is possible to account for this effect by computing the neutron heating
during various states of plasma operation (ramp-up, full-power, rampdown, dwell)
 Describe the neutron source geometry using 1D plasma transport
modelling + the contribution of fast ions (NBI, RF; dominant in JET!).
 The neutron source model can be refined progressively: thin annulus →
thermal plasma profile → thermal profile + fast ion contributions
 Neutronics calculation gives the volumetric heating of each component
 The heat source can be interfaced to Apros as an external module
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6/16/15
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TECHNOLOGY FOR BUSINESS