"PROJECTS FOR ENHANCING THE MUTUAL CO-OPERATION BETWEEN
ASSOCIATIONS"
e~êíãìí=_çÅâÉãΩÜä=EfmmF h.bockemuehl@fz-juelich.de
Trilateral Euregio Cluster (TEC)
Based on the expertise and the experimental facilities available, the collaboration within the TEC is concentrated on the joint exploitation of the TEXTOR device with special emphasis on:
a) exploration of stochastic plasmas with the Dynamic Ergodic Divertor, b) exploration of advanced tokamak scenarios, in particular with ECRH/ECCD,
c) fundamental studies of plasma-wall interaction and preparation of novel experiments for PSI studies (e.g. MAGNUM-PSI), and
d) development of new diagnostics.
Detailed results obtained in 2005 are found in chapters A – D of this report.
JET (partly supported by EFDA orders)
Though there was no experimental campaign at JET in 2005 due to reconstruction and the cancella-tion of C 15, Research Centre Jülich (FZJ) kept up its high level involvement by providing several colleagues under order up to an amount of 1.7 ppy, among those the project scientist for the ITER like wall project and the deputy leader of Task Force M.
Basic support for JET was carried out in 2005 up to an amount of about 2 ppy covered by respective notification within the association contract. This support dealt with a wide range of scientific tasks within the Task Forces S1, S2, E, M, D and T.
Research Centre Jülich kept playing a prominent role in the development of diagnostics for JET.
This is mainly done in the framework of the JET enhancement scheme (Quartz Micro Balance, Dis-ruption Mitigation Valve, ITER-like Wall project. Furthermore, FZJ was supporting JET operation by providing 4 professionals under secondment to the operator.
ITER / ITPA (partly supported by EFDA contracts) ITER modelling
A wide spectrum of theoretical and computational topics in magnetic fusion research has been cov-ered. This ranges from direct numerical support of experiments (3D tokamak magnetics, including island and stochastic layer formation, equilibrium reconstruction for TEXTOR-DED, W7-X,
rare-of turbulence on small scales and low (drift) frequencies, applied to the ergodized edge plasma layer of TEXTOR-DED.
Modelling of erosion and deposition with the ERO-code has been further improved by bench mark-ing with well defined experiments. Amounts of 13CH4 are injected and the evolution of deposition patterns is studied. The parallelisation of the ERO-code has been completed allowing now for a decrease of calculation time by about a factor of 5 to 10. Coupling with the Monte-Carlo code SDTrimSP allows now to simulate the dynamic change of the surface composition in mixed mate-rial systems. The modelling of experiments with beryllium in the linear plasma device PISCES has been started aiming at an improved understanding of deposition and erosion of mixed Be-C-W lay-ers. The ERO-code provides a key model for the prediction of the amount of tritium retention in ITER.
Major long term code developments at FZJ for the European fusion program, such as the ERO code for local erosion and re-deposition simulation, or the Monte Carlo neutral gas and radiation transfer code EIRENE, have been integrated in the JET and EFDA ITM (integrated tokamak modelling) task forces. The goals are both to standardise the data exchange formats between codes in Europe but also the quality control (code verification and validation). Both these codes are routinely applied to assist the ITER engineering design. A joint web based project between FZJ and the IAEA atomic data unit has been established to further improve the predictive quality of fusion plasma codes by developing appropriate and standardized atomic and molecular databases.
ITER diagnostic
The ongoing diagnostic developments are performed in close relation to the needs of ITER, in par-ticular in order to improve the physics base for ITER or to prepare for the construction phase of ITER.
– Laser induced desorption in deposited carbon layers is proposed as in-situ monitor diagnostics to determine the degree of tritium retention.
– The dispersion interferometer on TEXTOR is the first test of a new scheme for plasma density measurements. It could be ideal for ITER since it is robust against vibrations and thermal ex-pansion. In a next step of the collaboration with Budker Institute for Nuclear Physics in Novosi-birsk it is envisaged to implement the real-time calculation of the line-integrated electron den-sity.
– A CXRS system with ITER-relevant geometry (observation from the top) is now being mounted on TEXTOR. This system will allow the simultaneous measurement of the CXRS emission of different impurities, the beam emission and the motional Stark spectrum. The latter measure-ments make it possible to derive the current density profile, whereas the combination of the first two gives a direct measurement of the impurity profile.
– First direct comparative test of polycrystalline and single crystals as candidate diagnostic mir-rors for ITER have been tested in TEXTOR with respect to their long term reflectivity under load conditions.
– FZJ is also participating in a working group of the ITER team on the engineering of ITER port plugs and the integration of diagnostics therein.
Common projects on the use of the DED on impurity shielding by the dynamic ergodic divertor have been performed. The DED is designed for several modes of operation, the corresponding op-erational scenarios address various different aims. The experiments have shown that the m/n = 3/1 base mode of the DED is the best scenario for the investigation of tearing mode related topics, while the m/n = 12/4 and the m/n = 6/2 base modes are more suited for the divertor configuration studies.
The exploitation of the m/n = 6/2 mode just started at the end of 2005. The main results are obtained on the issues 1) divertor structure, 2) edge plasma rotation, 3) ELM-mitigation, 4) magneto-hydrodynamics (MHD) and 5) profile shaping. This is done in close collaboration with CEA and the tokamak DIII-D.
IPP (Max-Planck-Institute Garching and Greifswald)
According to its existing technical expertise, Research Centre Jülich has taken over comprehensive work packages for the construction of the Wendelstein 7-X stellarator.
Engineering
Superconducting Bus-System: The coils are interconnected by superconducting bus bars. The tech-nical specifications are the basis for the design, construction, qualification, manufacturing and as-sembly of the buses and their appropriate supports.
– A new bus topology was developed to avoid collisions with other parts and to facilitate the as-sembly. To check the geometry of the bent buses and to examine the buses assembly, a 1:1 model was manufactured and assembled.
– For the qualification of the insulation and the fabrication process different samples have been fabricated and a special examination procedure has been developed.
– For series production of the 125 buses a production line has been installed in Jülich. One of the most critical points to be solved was the handling of the up to 13m long 3-dimensional shaped bus bars. Test of production with dummy conductors has been finished and series production will start soon.
Bus support structure: The design of the support structure is based on different adjustable sub-modules which are able to compensate fabrication tolerances in all directions and to facilitate the assembly on site. Movement and forces acting on the buses are taking into account during several iterations of support design and stress calculations.
Joints: Approximately 230 low-resistance joints are required for electrical and hydraulic intercon-nections between superconductors at the coil terminals and between five adjacent modules. After design review three joints have been manufactured and tested under pressure. Resistance tests at 4 K are in preparation and after delivering of material the manufacturing of 230 joints including inner clamping parts will be started at FZJ.
Stress analysis: The structural analyses of the numerous options of the narrow support elements have been performed with finite element models. Requirements for the bus-bar supports have been developed. The design changes in the joint structure were modelled.
coils. In the course of the year, altogether 6 welding attempts were executed in order to determine and to optimize the occurring welding distortion. These welding tests guarantee that the weld qual-ity can also be executed on a high level at the experiment. The manufacture of the welds puts high demands on the dexterity of the executing welder. In February 2005 two welders of the IPP Greif-swald were trained in the FZJ.
Diagnostics
VUV spectrometer: In the course of 2005, the construction of the VUV spectrometer system HEXOS (High Efficiency XUV Overview Spectrometer) has been completed together all peripheral equipment such as mechanical stands, vacuum systems, detectors, cameras and data acquisition which are needed to perform the laboratory testing. The spectrometers have been assembled and aligned at the Horiba Jobin-Yvon laboratories. The spectral resolution is in agreement with the ex-pected instrumental width (0.13 nm FWHM) The alignment of the HEXOS 1 spectrometer was tested using a pinch discharge (by AIXUV GmbH, Aachen) burning in argon.
Hydrogen beam: A high energy hydrogen beam diagnostic injector is developed in cooperation with the Budker Institute of Nuclear Physics (BINP) in Novosibirsk. The beam shall provide an equiva-lent current of more than 5 A at 60 keV energy. During the whole duration of injection (i.e. 10 s) the beam properties the divergence should stay below 0.5º. The R&D work on optimisation of the grid structure for higher current densities and lower beam divergence of the ion optics was contin-ued on TEXTOR. The decision about the type ion source will be made based on their performance on an existing prototype at TEXTOR.
HAS
The Hungarian institute KFKI will apply a 35 keV lithium atom beam at TEXTOR for fluctuation and electron density profile measurements. The range of observation will cover about 12 cm from the LCFS towards the plasma centre that will overlay the most interesting part for operation with the DED. The implementation of the vacuum system including the ion source, the neutraliser and the beam line has been finished. The protection shielding and interlock circuit for safe operation with high voltage under remote conditions has also been designed.
The final design of the Li-beam in-vessel mirror system has been finished und manufacturing will be initiated soon. Installation is planned for the summer shutdown.
VR
The co-operation between FZJ/TEXTOR and VR Sweden concentrated to the field of plasma-wall interaction.
The investigations of fuel accumulation, carbon migration and materials mixing in gaps of castel-lated structures have been continued. The thickness of deposited layers has been determined and the corresponding fuel accumulation. Efforts for modelling these observations are ongoing.
A new system for the Nuclear Reaction Analysis (NRA) for post-mortem analysis of samples ex-posed to TEXTOR is to be installed at the tandem accelerator facility in FZJ (ISG) and will be op-erational in the beginning of 2006. The facility will allow for instant and complex surface investiga-tion of large tiles exposed in TEXTOR including limiters from heavy high-Z materials.
As the only present tokamak in the world, TEXTOR holds the capability of measuring the localised 1D distribution function of the confined fast ions using the technique of collective Thomson scatter-ing (CTS). This diagnostic had a breakthrough durscatter-ing 2000/2001 at TEXTOR usscatter-ing mm waves to scatter off the electron fluctuations. This diagnostic has now been upgraded at Risø and reinstalled at TEXTOR.
In 2005 the first results from the upgraded fast ion collective Thomson scattering system on TEX-TOR was achieved. The slowing down of neutral beam ions has been measured and shows good agreement with numerical simulations. Furthermore, the interaction between MHD instabilities and the fast ion distribution is being examined. These interactions are not well understood and experi-mental data are urgently needed to improve this understanding especially for ITER, where the amount of fast ions will be significant and MHD instabilities interacting with these will have to be limited.
F. STRUCTURE OF THE FZJFUSION PROGRAMME AND RELATED FIGURES
e~êíãìí=_çÅâÉãΩÜä=EfmmF h.bockemuehl@fz-juelich.de
Research Centre Jülich (FZJ)
Research Centre Jülich (FZJ) is one of the 15 Helmholtz Research Centres in Germany.
Structure
A new organisational structure of FZJ was set in force on May 18th, 2006. The main elements are as follows:
The Research Centre is being led by a single scientific and a single administrative member of the Board of Directors, which from now on will consist of only these two persons.
The research activities are organised in five research areas, coordinated and represented by Acting Research Directors: Structure of Matter, Key Technologies, Health, Earth and Envi-ronment, Energy (Acting Research Director here: Prof. Detlev Stöver).
The former 12 departments with 36 institutes and the 2 project managements are merged in one institute per research area.
Fusion Research is being carried out by the new Institute for Energy Research (IEF), in which the Institute for Plasma Physics (IPP), the Institute for Materials and Processes in Energy Systems (IWV) and the Nuclear Fusion Project (KFS) are integrated. The research activities are being sup-ported by the Central Department of Technology (ZAT) and the Operation Management (B) with its Hot Cell facilities.
Employees
• 4200, comprising about 1100 scientists, 400 PhD students, 150 undergraduates and 350 trainees in 20 professions.
• Visiting scientists: more than 700 each year from more than 50 countries.
Annual Budget
• 360 million Euro.
Trilateral Euregio Cluster (TEC)
The three EURATOM associated institutes for plasma physics in the Euregio (ERM/KMS Brussels, FOM Rijnhuizen, and Forschungszentrum Jülich) carry out a joint research programme in the framework of the Trilateral Euregio Cluster (TEC) with the Jülich tokamak TEXTOR serving as a central facility. TEC is being steered by the TEC directors, namely A. Kleyn, N. Lopes Cardozo, U.
Samm, R. Weynants, and R. Wolf.
Fusion Programme of FZJ
(still to be formally adapted to the new organisational structure)
The Nuclear Fusion Project (KFS) is responsible for the co-ordination of the fusion programme of Research Centre Jülich, its leader representing the Research Unit according to the Contract of Asso-ciation.
The Institute for Plasma Physics is fully devoted to fusion research and represents about 80% of the overall fusion programme of FZJ with special emphasis on the physics programme.
Structure
Part II: Plasma Core and Theory
The technological oriented part of the FZJ fusion programme is mainly carried out in the Institute for Materials and Processes in Energy Systems (IWV) under support of the Operation Management Department (B) with its Hot Cell Facility. Further technical support is given mainly by the Central Department of Technology (ZAT).
Relevant figures of the overall fusion programme of FZJ
Financial resources (in mio. €)
Consumables 1,8
Investments 1,4
Staffing (in PY including support by central departments)
Scientists 46
PhD students 12
Technical and administrative support 67
Sum 125
Visiting scientists yearly about 100
Estimated costs of the fusion programme (in mio.€)
Physics 17,4
Technology 2,0
Lecturing
• About 15 hours per week at 3 universities (Düsseldorf, Bochum, Duisburg-Essen)
• Carolus Magnus Summer School on Plasma Physics every 2 years (jointly organised by the TEC partner institutes)
Most important co-operations
• IEA Implementing Agreement on Plasma-Wall Interaction in TEXTOR
• Various collaborations with EURATOM-Associations (ERM/KMS and FOM within TEC, IPP Garching/Greifswald, CEA, RISØ, HAS, FZK, et al.) and in the framework of EFDA
• Numerous collaborations with national and international fusion laboratories and universities (with special emphasis on basic plasma physics with more than 10 universities in the Eure-gio)
G. LIST OF SCIENTIFIC PUBLICATIONS, TALKS AND POSTERS
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