Ion beam analysis methods in the studies of plasma facing materials in controlled fusion devices
|
|
- Charity Pope
- 6 years ago
- Views:
Transcription
1 Vacuum 70 (2003) Ion beam analysis methods in the studies of plasma facing materials in controlled fusion devices M. Rubel a, *, P. Wienhold b, D. Hildebrandt c a Alfv!en Laboratory, Royal Institute of Technology, Association EURATOM VR, Teknikringen 31, S Stockholm, Sweden b Institute of Plasma Physics, Forschungszentrum J.ulich, Association EURATOM, D J.ulich, Germany c Max Planck Institute of Plasma Physics, Diagnostic Division, Association EURATOM, D Berlin, Germany Abstract Application of ion beam analysis techniques in the studies of material transport and fuel inventory in the controlled fusion devices is exemplified. Enhanced proton scattering on the carbon isotopes 12 C(p,p) 12 C, 13 C(p,p) 13 C and secondary ion mass spectrometry allowed for determination of carbon erosion and re-deposition on the wall components following the experiments with a tracer ( 13 CH 4 ) injection into the plasma edge at the TEXTOR tokamak. For the assessment of the deuterium fuel accumulation in the plasma facing components depth profiling by means of nuclear reaction analysis, 3 He(d,p) 4 He, was performed. Advantages and limitations of those nuclear methods in solving experimental problems are addressed. r 2003 Elsevier Science Ltd. All rights reserved. Keywords: Ion beam analysis; Erosion; Deposition; Hydrogen inventory; Tokamak 1. Introduction High particle fluxes and resulting heat loads cause erosion and significant modification of material surfaces surrounding the plasma in the controlled fusion devices. Plasma material interaction (PMI) leads to degradation of plasma performance (power radiation losses) and properties of wall materials [1,2]. The contact of particles escaping a fusion plasma with the wall is unavoidable because the discharge duration is much longer than the particle confinement time (t p ). In spite of these negative effects, PMI is also a *Corresponding author. Tel.: ; fax: address: rubel@fusion.kth.se (M. Rubel). necessary condition for a future reactor operation. The wall has to extract injected power and to thermalise helium ash produced in the D T fusion process [3]. The major mechanisms of erosion are physical sputtering, chemical erosion and evaporation [1,2]. Eroded species become ionised in the plasma edge, they are transported along the magnetic field lines and eventually redeposited (co-deposited, co-implanted) in another location together with fuel atoms, i.e. hydrogen isotopes. Re-deposition results in material mixing [4,5] and retention of hydrogen isotopes. Fuel inventory is especially pronounced in tokamaks with the plasma facing components (PFC) made of carbon [2,6 8]. Accumulation of radioactive tritium in a next-step device must not exceed safety limits (350 g). Therefore, the studies of PMI in X/03/$ - see front matter r 2003 Elsevier Science Ltd. All rights reserved. doi: /s x(02)
2 424 M. Rubel et al. / Vacuum 70 (2003) Table 1 Ion beam analysis methods used in studies of plasma facing materials Isotope/ tracer Method/reaction Beam/energy (MeV) Information depth (mm) Remarks: advantages and limitations D NRA/ 3 He(d,p) 4 He 3 He + / Depth profiling (+) Very high selectivity (+) Sensitivity cm 2 (+) Ion-induced detrapping ( ) D d(p,p)d H + / Cross sections not well defined ( ) Depth profiling in thin layers 11 B NRA p( 11 B,a) 8 Be H + / High selectivity & sensitivity (+) No depth profiling ( ) 12 C EPS 12 C(p.p) 12 C H + /1.5 8 H + /1.748 (resonance) Around 0.1 * In case of mixed layers * 13 C EPS 13 C(p.p) 13 C H + /1.25 H + /1.442 (resonance) 6 Around 0.1 * In the presence of C-12, * quantification of C-13 possible only in thin layers and only at the resonance energy Si RBS 4 He + / Below 1 Mo RBS 4 He + / Below 1 Sensitivity: cm 2 W, Ta RBS 4 He + / Below 1 Very high sensitivity: cm 2 present-day experiments, operated predominantly with deuterium, are focused on material transport in order to determine the distribution and composition of erosion and deposition zones. This, in turn, allows for conclusions regarding the selection of wall materials and development of methods for fuel removal. The thickness of modified layers ranges from some nanometers to hundreds of microns dependent on the location in a fusion device and on the plasma operation time [9]. Characterisation of such layers is a mosaic work requiring application of various spectroscopy and microscopy techniques. Among them, the accelerator-based ion beam analysis (IBA) methods prove to be the most effective ones because of their sensitivity, selectivity, good lateral and depth resolution and, last but not least, the speed of analysis (important in mapping of large surfaces) as several various detectors can be simultaneously used. This paper is focused on the investigation of fusion reactor materials with nuclear reaction analysis (NRA), Rutherford backscattering spectroscopy (RBS) and enhanced proton scattering (EPS). Special emphasis is given to the application of IBA in the determination of carbon transport by means of a tracer technique ( 13 C marker) and, to the assessment of deuterium retention and distribution in PFC. In Table 1 we summarise some practical aspects regarding analyses of carbon, deuterium and some other elements (B, Si, W) used for wall conditioning [10] or power handling [2] in tokamaks. 2. Experimental procedure Experiments were carried out in the TEXTOR tokamak (Forschungszentrum J.ulich, Germany), a controlled fusion device with a circular plasma (a ¼ 46 cm) and several arrays of graphite limiters. The structure of inner wall components can be found in [11]. Carbon ( 12 C) is the major plasma impurity species and, therefore, for the studies of its transport mechanism a predetermined amount of 13 C tracer ( molecules of 13 CH 4 ) was injected into the plasma edge through an inlet hole in an aluminium plate located in the scrape-off layer (SOL) [12]. The aim was to determine the carbon deposition efficiency, i.e. the ratio of species deposited locally after a short range
3 M. Rubel et al. / Vacuum 70 (2003) transport in the vicinity of the gas inlet to the amount transported in the torus (long-range transport): 13 C s / 13 C l. The plate inclination by 201 with respect to the magnetic field lines, as shown in Fig. 1a, allowed for the determination of radial distributions of carbon species. To assess the ratio of 13 C/ 12 C after the long-range transport, a flux catcher plate was mounted on the same holder perpendicularly to the field lines. There was no magnetic connection between the two plates. Analysis of 13 C [13], 12 C [14] and deuterium [15,16] in co-deposits was performed at a scattering angle of 1701 by means of EPS at resonance energies and by NRA, respectively (see Table 1 for details). Resonance energies for protons scatteredoff on the two carbon isotopes are well separated (B300 kev), but relatively narrow (B1 kev) making the quantitative analysis and depth profiling in non-uniform mixed layers rather difficult because of the energy drop (stopping factor [e] B7eV cm 2 ) and corresponding sharp change of the reaction cross-section. Fortunately, equally high reaction cross-sections (1 b sr 1 at resonance in both cases) allow for the determination of the isotope ratio ( 13 C/ 12 C) with a high degree of confidence. The results were cross-checked by means of secondary ion mass spectrometry (SIMS) with a 10 kev oxygen beam. SIMS was also used to measure the total layer thickness. These results were compared with the NRA depth profiling of co-deposited deuterium. A 3 He + beam of energy of 0.75 MeV was used. Determination of deuterium inventory in PFC was carried out on tiles of the toroidal belt limiter. For probing thick layers formed in the deposition zone (structure shown in [9]) an energy scan from 0.7 to 2.5 MeV with a 3 He + beam was required to recognise the D content and its distribution. High energy protons (11 13 MeV range) emerging from the 3 He(d,p) 4 He reaction assure high selectivity of deuterium tracing and allow for high-resolution depth profiling [17]. The accessible analysis depth in a carbon matrix extends to around mm with a 2.5 MeV beam. These features make the reaction attractive not only in fusion science but also in other fields whenever deuterium may be used as a non-radioactive marker in the studies of hydrogen behaviour in solids. Another reaction PLASMA last closed flux surface Al plate α = 20 o 13 CH4 inlet for deuterium analysis, D(p,p)D [18,19], is cheaper than the one involving 3 He, but depth profiling is limited. 3. Results and discussion flux catcher plate Scrape-off layer Fig. 1. Schematics of the experimental set-up used for the studies of carbon transport at TEXTOR. Images in Fig. 2a and b show the plates after their exposure during the plasma discharges with 13 CH 4 injection. An optical analysis of interference fringes (method explained in [20]) indicates the layer thickness ranging from at least 40 nm to over 170 nm. From the isotopic ratio 13 C/ 12 C determined with EPS (results plotted in Fig. 3a) one infers a distribution of locally re-deposited 13 C (injected) and 12 C eroded from the wall and deposited from the plasma. The ratio reaches its maximum value near the gas inlet and then decreases, both towards the plasma and further into the SOL, indicating a high background deposition of C-12 from the plasma. Already at the distance of a few centimetres from the inlet a very small amount of 13 C is detected. The integrated amount of 13 C found on the plate corresponds to only 1% of the total gas input ( 13 C s / 13 C l =0.01) [12,21]. The rest becomes ionised and transported to other locations in the torus, i.e. to the deposition zones on the blades and neutraliser plates of a toroidal belt limiter [22]. Indeed, surface analysis of the flux catcher probe revealed a significant fraction of C-13 involved in the long-range transport, 13 C/ 12 C=0.27 independent of the radial distance with respect to the plasma. The results prove that the prevailing fraction of eroded carbon is transported by the plasma. This is unlike in case of eroded high-z
4 426 M. Rubel et al. / Vacuum 70 (2003) Carbon deposit (a) Gas inlet (b) Fig. 2. Deposition pattern on the aluminium plates following the 13 CH 4 injection into the plasma edge: (a) Plate with the gas inlet hole. White dotted line corresponds to the line of analysis; (b) Flux catcher plate. metals, which become promptly and locally redeposited [4,23,24]. While the measurements of the isotope ratio with EPS and SIMS yielded the same results, the total thickness of mixed carbon deposits could not be quantified with EPS alone (at resonance energies) for the layers thicker than 100 nm for the reasons explained in Section 2. This discrepancy is exemplified in Fig. 3b revealing that the agreement in the determination of the total layer thickness, i.e. 13 C+ 12 C, is obtained for thin layers, only. Moreover, the plots prove that the maximum of carbon content is detected closer to the plasma edge and deposition is strongly dominated by 12 C impurities eroded from PFC. The distribution of co-deposited deuterium has been found similar to the thickness profile shown in Fig. 3b. Inspection of the TEXTOR in-vessel components indicates that the re-deposition of eroded material occurs mainly on some areas of the blades (layer growth rate B3 nm/s) and on the neutraliser plates (B11 nm/s) of the toroidal belt limiter. Therefore, during hours of plasma operation the layers reached thickness of up to 1 mm [9]. Though the composition of co-deposits is a complex mixture of elements [23,25], the analysis of such structures is mainly focused on the total fuel inventory and distribution (lateral and depth) of hydrogen isotopes. While the quantitative IBA measurements of hydrogen 15 N(p,a) 12 C and tritium 3 He(t,d) 4 He in thick layers meet some practical difficulties, the deuterium content can be conclusively determined. The plots in Fig. 4a and b exemplify deuterium depth distribution in the deposition and erosion zones on the limiter tiles. In the deposition zone the deuterium content reaches nearly D at cm 2 and the distribution of the isotope is fairly uniform indicating that the presence of deuterium extends outside the accessible analysis depth with the applied He-3 beam (primary energy of 1.5 MeV in this case). The analysis with the beam energy increased to 2.5 MeV performed on both sides (front and rear sides) of the layer detached from the tile allowed for the determination of the amount of deuterium fuel trapped in the co-deposit. Knowing the layer thickness and the total area of the deposition zone (B1m 2 ) on that limiter, the total content of deuterium could be estimated ( D atoms). The result was cross-checked with thermal desorption spectrometry measurements showing an agreement within 8%. In the erosion zone, the narrow distribution and small amount of deuterium detected predominantly in the near-surface layer is attributed to the implanted species. The tail extended to several microns is related both to
5 M. Rubel et al. / Vacuum 70 (2003) RATIO C 13 /C 12 (a) THICKNESS [nm] (b) DISTANCE ACROSS THE SURFACE [mm] 49.5 RADIAL DISTANCE FROM PLASMA CENTER [cm] inlet hole RADIAL DISTANCE FROM PLASMA CENTER [cm] inlet hole SIMS EPS DISTANCE ACROSS THE SURFACE [mm] Fig. 3. Distribution of carbon isotopes in the deposit on the aluminium plate exposed to the scrape-off layer plasma during the 13 CH 4 injection: (a) 13 C/ 12 C isotope ratio determined with EPS; (b) comparison of total amount of carbon ( 13 C+ 12 C) on the Al plate measured with EPS at resonance energies and with SIMS. the surface roughness and to the in-depth migration of implanted fuel into the carbon substrate [26,27]. By repetition of this analytical procedure for studying material re-deposited in other locations of TEXTOR (i.e. other limiters and neutraliser plates) the overall deuterium inventory in the device was determined. Deuterium atomic density (10 22 cm _ 3 ) (a) E(0) 3 He + = 1.5 MeV Deposition 3zone C(D) (microns) = 4.78 x cm -2 Erosion zone 3 C(D) (microns) = 2.02 x cm -2 (b) Depth (microns) Fig. 4. Deuterium depth distribution and concentration in: (a) deposition, and (b) erosion zones on the toroidal belt limiter at TEXTOR. The results of analysis allow for the conclusions regarding fuel inventory (amount and distribution), surface modification of PFC and material transport in fusion devices. The 13 C tracer experiment followed by measurements of carbon isotopes resulted in the quantitative distinction of the long and short range impurity transport. It has been clearly shown that in the erosion of carbon, long-range transport prevails in the formation of co-deposits. From the analytical point of view, the proton scattering technique applied to the mixed carbon films has yielded conclusive results regarding the isotope ratio, but the determination of the total layer thickness (over 100 nm) must be complemented by sputter-assisted measurements, e.g. SIMS as applied in this work. In the analysis of deuterium in co-deposits 3 He(d,p) 4 He reaction yields reliable results. The challenge to determine the total inventory in a controlled fusion device is not on the physics side, but the necessity of mapping of a large number of large components from various locations. The results help the assessment of tritium inventory in a future D T operated reactor. 4. Summary and conclusions Acknowledgements This work was partly supported by NFR Contract F /2000.
6 428 M. Rubel et al. / Vacuum 70 (2003) References [1] Philipps V. In: Hofer WO, Roth J, editors. Physical Processes of the Interaction of Fusion Plasmas with Solids. New York: Academic Press, [2] Federici G, et al. Nucl Fusion 2001;41: [3] Philipps V, Wienhold P, Kirschner A, Rubel M. Erosion and re-deposition of wall materials in controlled fusion devices. Vacuum 2002;67: [4] Rubel M, et al. J Nucl Mater 2000; : [5] Linsmeier C, Luthin J, GoldstraX P. J Nucl Mater 2001; : [6] Coad JP, Andrew PL, Peacock AT. Phys Scr 1999;T81: [7] Mayer M, et al. J Nucl Mater 2001;20 293: [8] Rubel M, et al. Beryllium and carbon films at JET following D-T operation. 15th International Conference on Plasma Surface Interactions in Controlled Fusion Devices, Gifu, Japan, May J Nucl Mater, in press. [9] Rubel M, et al. Thick co-deposits on plasma facing components in controlled fusion devices with carbon walls. International Workshop on Hydrogen Isotopes in Fusion Reactor Materials, Tokyo, May 2002, Phys Scr, in press. [10] Winter J, et al. Phys Rev Lett 1993;71: [11] Miyasaka K, et al. J Nucl Mater 2001; : [12] Wienhold P, et al. J Nucl Mater 2001; : [13] Milne EA. Phys Rev 1954;93: [14] Jackson HL, et al. Phys Rev 1953;89: [15] Altstetter CJ, et al. Nucl Instrum Methods 1978;149: [16] Khabibullaev PK, Skorodumov BG. Determination of Hydrogen in Materials, Nuclear Physics Methods, Springer Tracks in Modern Physics, vol. 117, Berlin: Springer. [17] Fried T. Ph.D. thesis, Surface Studies for Fusion Research Using Ion Backscattering Spectroscopy, Research Institute of Physics, Stockholm, Sweden, [18] Sherr R, et al. Phys Rev 1947;72: [19] Cocher DC, Clegg TB. Nucl Phys A 1969;132: [20] Wienhold P, Weschenfelder F, Winter J. Nucl Instrum Methods B 1994;94: [21] Wienhold P, et al., Short and long range transport of materials eroded from wall components in fusion devices. J Nucl Mater, in press. [22] Kirschner A, et al. J Nucl Mater 2001; : [23] Rubel M, et al. J Nucl Mater 1997;249: [24] Naujoks D, Behrisch R. J Nucl Mater 1995; : [25] Behrisch R, et al. J Nucl Mater 1987; : [26] Emmoth B, Rubel M, Franconi F. Nucl Fusion 1990;30: [27] Rubel M, et al. J Nucl Mater 1992; :
ANALYSIS OF PLASMA FACING MATERIALS IN CONTROLLED FUSION DEVICES. Marek Rubel
ANALYSIS OF PLASMA FACING MATERIALS IN CONTROLLED FUSION DEVICES Marek Rubel Alfvén Laboratory, Royal Institute of Technology, Association EURATOM VR, Stockholm, Sweden Acknowledgements Paul Coad and Guy
More informationIn-vessel Tritium Inventory in ITER Evaluated by Deuterium Retention of Carbon Dust
FT/P1-19 In-vessel Tritium Inventory in ITER Evaluated by Deuterium Retention of Carbon Dust T. Hino 1), H. Yoshida 1), M. Akiba 2), S. Suzuki 2), Y. Hirohata 1) and Y. Yamauchi 1) 1) Laboratory of Plasma
More informationCarbon Deposition and Deuterium Inventory in ASDEX Upgrade
1 IAEA-CN-116 / EX / 5-24 Carbon Deposition and Deuterium Inventory in ASDEX Upgrade M. Mayer 1, V. Rohde 1, J. Likonen 2, E. Vainonen-Ahlgren 2, J. Chen 1, X. Gong 1, K. Krieger 1, ASDEX Upgrade Team
More information1 EX/P4-8. Hydrogen Concentration of Co-deposited Carbon Films Produced in the Vicinity of Local Island Divertor in Large Helical Device
1 EX/P4-8 Hydrogen Concentration of Co-deposited Carbon Films Produced in the Vicinity of Local Island Divertor in Large Helical Device T. Hino 1,2), T. Hirata 1), N. Ashikawa 2), S. Masuzaki 2), Y. Yamauchi
More informationERO modelling of local deposition of injected 13 C tracer at the outer divertor of JET
ERO modelling of local deposition of injected 13 C tracer at the outer divertor of JET M I Airila 1, L K Aho-Mantila 2, S Brezinsek 3, J P Coad 4, A Kirschner 3, J Likonen 1, D Matveev 3, M Rubel 5, J
More informationDeuterium and Hydrogen Retention Properties of the JT-60 and JT-60U Divertor Tiles
Deuterium and Hydrogen Retention Properties of the JT-60 and JT-60U Divertor Tiles Y. Hirohata 1), T. Tanabe 2), Y. Oya 3), K. Shibahara 4), M. Oyaidzu 5), T. Arai 6), K. Masaki 6), Y. Gotoh 6), K. Okuno
More informationEstimation of the contribution of gaps to tritium retention in the divertor of ITER
Estimation of contribution of gaps to tritium retention in the divertor of ITER 1 Estimation of the contribution of gaps to tritium retention in the divertor of ITER 1. Introduction D. Matveev 1,2, A.
More informationMax-Planck-Institut für Plasmaphysik, EURATOM Association POB 1533, D Garching, Germany
DEPTH PROFILE REONSTRUTION FROM RUTHERFORD BAKSATTERING DATA U. V. TOUSSAINT, K. KRIEGER, R. FISHER, V. DOSE Max-Planck-Institut für Plasmaphysik, EURATOM Association POB 1533, D-8574 Garching, Germany
More informationDeposition and re-erosion studies by means of local impurity injection in TEXTOR
Deposition and re-erosion studies by means of local impurity injection in TEXTOR A. Kirschner a*, A. Kreter a, P. Wienhold a, S. Brezinsek a, J.W. Coenen a, H.G. Esser a, A. Pospieszczyk a, Ch. Schulz
More informationElastic Recoil Detection Method using DT Neutrons for Hydrogen Isotope Analysis in Fusion Materials. Abstract
Elastic Recoil Detection Method using DT Neutrons for Hydrogen Isotope Analysis in Fusion Materials Naoyoshi Kubota, Kentaro Ochiai, Keitaro Kondo 2 and Takeo Nishitani. :Japan Atomic Energy Research Institute,
More informationOverview of comprehensive characterisation of erosion zones on plasma facing components
Fusion Engineering and Design 81 (2006) 211 219 Overview of comprehensive characterisation of erosion zones on plasma facing components M.J. Rubel a,, E. Fortuna b, A. Kreter c, E. Wessel d, V. Philipps
More informationAMS MEASUREMENTS OF DEUTERIUM CAPTURED IN TUNGSTEN LAYERS DEPOSITED BY MAGNETRON SPUTTERING
Romanian Reports in Physics, Vol. 65, No. 4, P. 1258 1264, 2013 AMS MEASUREMENTS OF DEUTERIUM CAPTURED IN TUNGSTEN LAYERS DEPOSITED BY MAGNETRON SPUTTERING A.R. PETRE 1,3, T. ACSENTE 2, M. ENACHESCU 1,
More informationChemical Sputtering of Carbon Materials due to Combined Bombardment by Ions and Atomic Hydrogen
Chemical Sputtering of Carbon Materials due to Combined Bombardment by Ions and Atomic Hydrogen W. Jacob, C. Hopf, and M. Schlüter Max-Planck-Institut für Plasmaphysik, EURATOM Association, Boltzmannstr.
More informationHydrocarbon transport in the MkIIa divertor of JET
INSTITUTE OF PHYSICS PUBLISHING Plasma Phys. Control. Fusion 45 (23) 39 319 PLASMA PHYSICS AND CONTROLLED FUSION PII: S741-3335(3)37188-X Hydrocarbon transport in the MkIIa divertor of JET A Kirschner
More informationEU Plasma-Wall Interactions Task Force
Recent results on material migration and fuel retention in JET V. Philipps and JET TFE co-workers* Overview on present results on erosion, deposition and fuel retention in last JET campaign (2001-2004,C5-C15)
More informationGlobal migration of impurities in tokamaks: what have we learnt?
Global migration of impurities in tokamaks: what have we learnt? Euratom-Tekes Annual Seminar Silja Serenade, 28 May, 2013 Antti Hakola, Markus Airila and many others VTT Technical Research Centre of Finland
More informationList of Papers. P. Petersson, H. Bergsåker, G. Possnert, J.P. Coad, J. Likonen, S. Koivuranta, A. Hakola, and JET-EFDA Contributors
List of Papers This thesis is based on the following papers: I II III IV V VI Measurement of hydrogen isotopes by a nuclear microprobe P. Petersson, J. Jensen, A. Hallén and G. Possnert J. Phys.: Conf.
More information1 EX/3-5. Material Erosion and Redeposition during the JET MkIIGB-SRP Divertor Campaign
1 Material Erosion and Redeposition during the JET MkIIGB-SRP Divertor Campaign A. Kirschner 1), V. Philipps 1), M. Balden 2), X. Bonnin 3), S. Brezinsek 1), J.P. Coad 4), D. Coster 2), S.K. Erents 4),
More informationMicroanalysis of deposited layers in the divertor of JET with ITER-like wall
EUROFUSION WPJET2-PR(16) 14834 Y Zhou et al. Microanalysis of deposited layers in the divertor of JET with ITER-like wall Preprint of Paper to be submitted for publication in 22nd International Conference
More informationImplantation Energy Dependence on Deuterium Retention Behaviors for the Carbon Implanted Tungsten
J. Plasma Fusion Res. SERIES, Vol. 10 (2013) Implantation Energy Dependence on Deuterium Retention Behaviors for the Carbon Implanted Tungsten Yasuhisa Oya 1) *, Makoto Kobayashi 1), Naoaki Yoshida 2),
More informationHelium effects on Tungsten surface morphology and Deuterium retention
1 Helium effects on Tungsten surface morphology and Deuterium retention Y. Ueda, H.Y. Peng, H. T. Lee (Osaka University) N. Ohno, S. Kajita (Nagoya University) N. Yoshida (Kyushu University) R. Doerner
More informationModelling of Carbon Erosion and Deposition in the Divertor of JET
EFDA JET CP(01)02-64 A. Kirschner, V. Philipps, P. Wienhold, W. Fundamenski, G. Matthews, P. Coad, M. Stamp, D. Coster, D. Elder, P. Stangeby and JET EFDA Contributors Modelling of Carbon Erosion and Deposition
More informationGlobal Erosion and Deposition Patterns in JET with the ITER-like Wall
CCFE-PR(15)25 A.Baron-Wiechec, A.Widdowson, E.Alves, C.F.Ayres, N. P. Barradas, S.Brezinsek, J.P.Coad, N.Catarino, K.Heinola, J.Likonen, G.F.Matthews, M.Mayer, P. Petersson, M.Rubel, W. van Renterghem,
More informationTokamak Divertor System Concept and the Design for ITER. Chris Stoafer April 14, 2011
Tokamak Divertor System Concept and the Design for ITER Chris Stoafer April 14, 2011 Presentation Overview Divertor concept and purpose Divertor physics General design considerations Overview of ITER divertor
More informationEffect of the Surface Temperature on Net Carbon Deposition and Deuterium Co-deposition in the DIII-D Divertor
Effect of the Surface Temperature on Net Carbon Deposition and Deuterium Co-deposition in the DIII-D Divertor Presented by Dmitry Rudakov (UCSD) for the DiMES Team and Collaborators Presented at the 47th
More informationElectrode and Limiter Biasing Experiments on the Tokamak ISTTOK
Electrode and Limiter Biasing Experiments on the Tokamak ISTTOK C. Silva, H. Figueiredo, J.A.C. Cabral,, I. Nedzelsky, C.A.F. Varandas Associação Euratom/IST, Centro de Fusão Nuclear, Instituto Superior
More informationChemical Erosion and Critical Issues for ITER
Chemical Erosion and Critical Issues for ITER J. Roth Max-Planck-Institut für Plasmaphysik, Garching Chemical Erosion Studies Erosion yields: Dependence on temperature, energy and flux Emitted hydrocarbons
More informationPlasma Wall Interactions in Tokamak
Plasma Wall Interactions in Tokamak Dr. C Grisolia, Association Euratom/CEA sur la fusion, CEA/Cadarache Outline 1. Conditions for Fusion in Tokamaks 2. Consequences of plasma operation on in vessel materials:
More information31704 Dynamic Monte Carlo modeling of hydrogen isotope. reactive-diffusive transport in porous graphite
31704 Dynamic Monte Carlo modeling of hydrogen isotope reactive-diffusive transport in porous graphite * R. Schneider a, A. Rai a, A. Mutzke a, M. Warrier b,e. Salonen c, K. Nordlund d a Max-Planck-Institut
More informationDeuterium Inventory in Tore Supra: status of post mortem analyses
Deuterium Inventory in Tore Supra: status of post mortem analyses T. Dittmar a,*, P. Roubin d, E. Tsitrone a, E. Gauthier a, A. Hakola c, J. Likonen c, F. Linez a, C. Martin d, M. Mayer b, C. Pardanaud
More informationIsotope Exchange in High Heat-flux Components of the JET Tritium Neutral Beam Injector
JET CP(98)39 Isotope Exchange in High Heat-flux Components of the JET Neutral Beam Injector D Ciric, H P L de Esch, H-D Falter, T T C Jones, L Svensson. JET Joint Undertaking, Abingdon, Oxfordshire, OX14
More informationDIVIMP simulation of W transport in the SOL of JET H-mode plasmas
DIVIMP simulation of W transport in the SOL of JET H-mode plasmas A. Järvinen a, C. Giroud b, M. Groth a, K. Krieger c, D. Moulton d, S. Wiesen e, S. Brezinsek e and JET- EFDA contributors¹ JET-EFDA, Culham
More informationHigh-Precision Evaluation of Ultra-Shallow Impurity Profiles by Secondary Ion Mass Spectrometry
High-Precision Evaluation of Ultra-Shallow Impurity Profiles by Secondary Ion Mass Spectrometry Yoko Tada Kunihiro Suzuki Yuji Kataoka (Manuscript received December 28, 2009) As complementary metal oxide
More informationSTEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-60U
Abstract STEADY-STATE EXHAUST OF HELIUM ASH IN THE W-SHAPED DIVERTOR OF JT-6U A. SAKASAI, H. TAKENAGA, N. HOSOGANE, H. KUBO, S. SAKURAI, N. AKINO, T. FUJITA, S. HIGASHIJIMA, H. TAMAI, N. ASAKURA, K. ITAMI,
More informationNuclear Reaction Analysis (NRA)
Nuclear Reaction Analysis (NRA) M. Mayer Max-Planck-Institut für Plasmaphysik, EURATOM Association, Garching, Germany Lectures given at the Workshop on Nuclear Data for Science and Technology: Materials
More informationThomas Schwarz-Selinger. Max-Planck-Institut for Plasmaphysics, Garching Material Science Division Reactive Plasma Processes
Max-Planck-Institut für Plasmaphysik Thomas Schwarz-Selinger Max-Planck-Institut for Plasmaphysics, Garching Material Science Division Reactive Plasma Processes personal research interests / latest work
More informationJacob s Ladder Controlling Lightning
Host: Fusion specialist: Jacob s Ladder Controlling Lightning PART 1 Jacob s ladder demonstration Video Teacher resources Phil Dooley European Fusion Development Agreement Peter de Vries European Fusion
More informationLITHIUM DIAGNOSTIC BEAM DEVELOPMENT FOR FUSION PLASMA MEASUREMENTS PhD thesis GÁBOR ANDA. Thesis Supervisor: DR. SÁNDOR ZOLETNIK MTA KFKI RMKI
LITHIUM DIAGNOSTIC BEAM DEVELOPMENT FOR FUSION PLASMA MEASUREMENTS PhD thesis GÁBOR ANDA Thesis Supervisor: DR. SÁNDOR ZOLETNIK MTA KFKI RMKI Departmental supervisor: DR. GÁBOR PÓR BME NTI BUDAPEST UNIVERSITY
More informationEffect of Spiral Microwave Antenna Configuration on the Production of Nano-crystalline Film by Chemical Sputtering in ECR Plasma
THE HARRIS SCIENCE REVIEW OF DOSHISHA UNIVERSITY, VOL. 56, No. 1 April 2015 Effect of Spiral Microwave Antenna Configuration on the Production of Nano-crystalline Film by Chemical Sputtering in ECR Plasma
More informationAssessment of Erosion, deposition and fuel retention in the JET-ILW divertor from Ion Beam Analysis data
EUROFUSION WPJET2-PR(16) 14813 N Catarino et al. Assessment of Erosion, deposition and fuel retention in the JET-ILW divertor from Ion Beam Analysis data Preprint of Paper to be submitted for publication
More informationEROSION AND DEPOSITION MECHANISMS IN FUSION PLASMAS. A. Kirschner
EROSION AND DEPOSITION MECHANISMS IN FUSION PLASMAS A. Kirschner Institut für Energieforschung (Plasmaphysik), Forschungszentrum Jülich GmbH, Association EURATOM-FZJ, Trilateral Euregio Cluster, 52425
More informationFlux & Energy Dependence of Methane Production From Graphite Due to H + Impact
0.9^07090 Canadian Fusion Fuels Technology Project Flux & Energy Dependence of Methane Production From Graphite Due to H + Impact AUTHORS: J.W. Davis, A.A. Haasz, P.C. Stangeby University of Toronto Institute
More informationCATHODE MATERIAL CHANGE AFTER DEUTERIUM GLOW DISCHARGE EXPERIMENTS
Savvatimova, I., Y. Kucherov, and A.B. Karabut. Cathode Material Change after Deuterium Glow Discharge Experiments. in Fourth International Conference on Cold Fusion. 1993. Lahaina, Maui: Electric Power
More informationMolecular Dynamics Study of Plasma Surface Interactions for Mixed Materials
J. Plasma Fusion Res. SERIES, Vol. 9 () Molecular Dynamics Study of Plasma Surface Interactions for Mixed Materials Kaoru OHYA, Naohide MOHARA, Kensuke INAI, Atsushi ITO, Hiroaki NAKAMURA, Yoshio UEDA
More informationCharacterization of heated dust particles using infrared and dynamic images in LHD
1 EX/P4-7 Characterization of heated dust particles using infrared and dynamic images in LHD N Ashikawa 1), Y. Tomita 1), S. Masuzaki 1), A. Sagara 1), G. Kawamura 1), K. Nishimura 1), N. Ohno ) and LHD
More informationTARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D
GA A25445 TARGET PLATE CONDITIONS DURING STOCHASTIC BOUNDARY OPERATION ON DIII D by J.G. WATKINS, T.E. EVANS, C.J. LASNIER, R.A. MOYER, and D.L. RUDAKOV JUNE 2006 QTYUIOP DISCLAIMER This report was prepared
More informationTHERMAL OXIDATION EXPERIMENTS TO UNDERSTAND TRITIUM RECOVERY IN DIII-D, JET, C-MOD, AND MAST
GA A25482 13 C-TRACER EXPERIMENTS IN DIII-D PRELIMINARY IN THERMAL OXIDATION EXPERIMENTS TO UNDERSTAND TRITIUM RECOVERY IN DIII-D, JET, C-MOD, AND MAST by P.C. STANGEBY, S.L. ALLEN, N. BEKRIS, N.H. BROOKS,
More informationEffect ofe B driven transport on the deposition of carbon in the outer divertor of ASDEX Upgrade
Effect ofe B driven transport on the deposition of carbon in the outer divertor of ASDEX Upgrade 0-29 L. Aho-Mantila a,b *, M. Wischmeier c, K. Krieger c, V. Rohde c, H.W. Müller c, D.P. Coster c, M. Groth
More informationDivertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET
Journal of Nuclear Materials 363 365 (2007) 989 993 www.elsevier.com/locate/jnucmat Divertor power deposition and target current asymmetries during type-i ELMs in ASDEX Upgrade and JET T. Eich a, *, A.
More informationPlasma-wall interaction studies in the full-w ASDEX Upgrade during helium plasma discharges
1 P6-349 Plasma-wall interaction studies in the full-w ASDEX Upgrade during helium plasma discharges A. Hakola 1, S. Brezinsek 2, D. Douai 3, M. Balden 4, V. Bobkov 4, D. Carralero 4, H. Greuner 4, A.
More informationToward the Realization of Fusion Energy
Toward the Realization of Fusion Energy Nuclear fusion is the energy source of the sun and stars, in which light atomic nuclei fuse together, releasing a large amount of energy. Fusion power can be generated
More informationAtomic physics in fusion development
Atomic physics in fusion development The next step in fusion development imposes new requirements on atomic physics research by R.K. Janev In establishing the scientific and technological base of fusion
More informationInfluence of Amorphous Carbon Deposition on the Probability for Recombination of Neutral Oxygen Atoms on Aluminium Surfaces
Influence of Amorphous Carbon Deposition on the Probability for Recombination of Neutral Oxygen Atoms on Aluminium Surfaces A. Drenik, A. Vesel Center of Excellence for Polymer Materials and Technologies
More informationIon Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device
Ion Heating Experiments Using Perpendicular Neutral Beam Injection in the Large Helical Device Kenichi NAGAOKA, Masayuki YOKOYAMA, Yasuhiko TAKEIRI, Katsumi IDA, Mikiro YOSHINUMA, Seikichi MATSUOKA 1),
More informationAPPLICATION OF THE NUCLEAR REACTION ANALYSIS FOR AGING INVESTIGATIONS
1 APPLICATION OF THE NUCLEAR REACTION ANALYSIS FOR AGING INVESTIGATIONS G.Gavrilov, A.Krivchitch, V.Lebedev PETERSBURG NUCLEAR PHYSICS INSTITUTE E-mail: lebedev@pnpi.spb.ru kriv@rec03.pnpi.spb.ru We used
More informationDynamic Monte-Carlo modeling of hydrogen isotope reactive diffusive transport in porous graphite
Journal of Nuclear Materials 367 37 (27) 238 242 www.elsevier.com/locate/jnucmat Dynamic Monte-Carlo modeling of hydrogen isotope reactive diffusive transport in porous graphite R. Schneider a, *, A. Rai
More informationInteractions between ion thruster plumes and vessel walls
Interactions between ion thruster plumes and vessel walls IEPC-2013-xxx Presented at the 33 rd International Electric Propulsion Conference, The George Washington University, Washington, D.C., USA J. Duras,
More informationKonrad Klages. Deuterium Retention in Carbon, Beryllium, and Carbon Layers on Titanium and Beryllium
Konrad Klages Deuterium Retention in Carbon, Beryllium, and Carbon Layers on Titanium and Beryllium IPP 17/9 Juni, 2008 Deuterium Retention in Carbon, Beryllium, and Carbon Layers on Titanium and Beryllium
More informationErosion of tungsten and carbon markers in the outer divertor of ASDEX Upgrade
Article published in Physica Scripta T128 (2007) 106 Erosion of tungsten and carbon markers in the outer divertor of ASDEX Upgrade M Mayer 1, V Rohde 1, G Ramos 2, E Vainonen-Ahlgren 3, J Likonen 3, J
More informationApplicability of Laser-Induced Desorption Quadruple Mass Spectrometry (LID-QMS) for the Determination of Local Deuterium Retention
Applicability of Laser-Induced Desorption Quadruple Mass Spectrometry (LID-QMS) for the Determination of Local Deuterium Retention Reinier Zoomers June 2013 Supervisors: Dr. Pedro Zeijlmans van Emmichoven
More informationSecondaryionmassspectrometry
Secondaryionmassspectrometry (SIMS) 1 Incident Ion Techniques for Surface Composition Analysis Mass spectrometric technique 1. Ionization -Electron ionization (EI) -Chemical ionization (CI) -Field ionization
More informationPower Deposition Measurements in Deuterium and Helium Discharges in JET MKIIGB Divertor by IR-Thermography
EFDA JET CP(02)01/03 T Eich, A Herrmann, P Andrew and A Loarte Power Deposition Measurements in Deuterium and Helium Discharges in JET MKIIGB Divertor by IR-Thermography . Power Deposition Measurements
More informationITER A/M/PMI Data Requirements and Management Strategy
ITER A/M/PMI Data Requirements and Management Strategy Steven Lisgo, R. Barnsley, D. Campbell, A. Kukushkin, M. Hosokawa, R. A. Pitts, M. Shimada, J. Snipes, A. Winter ITER Organisation with contributions
More informationModelling of prompt deposition of tungsten under fusion relevant conditions
EUROFUSION WPPFC-CP(16) 1532 A Kirschner et al. Modelling of prompt deposition of tungsten under fusion relevant conditions Preprint of Paper to be submitted for publication in Proceedings of 26th IAEA
More informationAir exposure and sample storage time influence on hydrogen release from tungsten
Air exposure and sample storage time influence on hydrogen release from tungsten K.A. Moshkunov a, K. Schmid b, M. Mayer b, V.A. Kurnaev a, Yu.M. Gasparyan a a National research nuclear university MEPhI,
More informationSearch for Nuclear Reaction Products in Gas Phase Experiments - Deuterium Permeation and Absorption -
Session 3 O_2 Nuclear Measurements (I) Search for Nuclear Reaction Products in Gas Phase Experiments - Deuterium Permeation and Absorption - A. Kitamura 1, Y. Sasaki 1, Y. Miyoshi 1, Y. Yamaguchi 1, A.
More informationMeasurements of rotational transform due to noninductive toroidal current using motional Stark effect spectroscopy in the Large Helical Device
REVIEW OF SCIENTIFIC INSTRUMENTS 76, 053505 2005 Measurements of rotational transform due to noninductive toroidal current using motional Stark effect spectroscopy in the Large Helical Device K. Ida, a
More informationSilver Thin Film Characterization
Silver Thin Film Characterization.1 Introduction Thin films of Ag layered structures, typically less than a micron in thickness, are tailored to achieve desired functional properties. Typical characterization
More informationMolecular Dynamics Simulation of Chemical Sputtering of Hydrogen Atom on Layer Structured Graphite
1 TH/7-1 Molecular Dynamics Simulation of Chemical Sputtering of Hydrogen Atom on Layer Structured Graphite A. Ito 1,2), Y. Wang 1), S. Irle 1), K. Morokuma 3), and H. Nakamura 2) 1) Nagoya University,
More informationHydrogenic retention of high-z refractory metals exposed to ITER divertor relevant plasma conditions
1 Hydrogenic retention of high-z refractory metals exposed to ITER divertor relevant plasma conditions G.M. Wright 1), E. Alves 2), L.C. Alves 2), N.P. Barradas 2), M. Mayer 3), G.J. van Rooij 1), R.S.
More informationEstimating the plasma flow in a recombining plasma from
Paper P3-38 Estimating the plasma flow in a recombining plasma from the H α emission U. Wenzel a, M. Goto b a Max-Planck-Institut für Plasmaphysik (IPP) b National Institute for Fusion Science, Toki 509-5292,
More informationPlasma interactions with Be surfaces
Plasma interactions with Be surfaces R. P. Doerner and D. Nishijima for members of the Team Center for Energy Research, University of California San Diego, USA Work performed as part of: Plasma-Surface
More informationIon Implanter Cyclotron Apparatus System
Ion Implanter Cyclotron Apparatus System A. Latuszyñski, K. Pyszniak, A. DroŸdziel, D. M¹czka Institute of Physics, Maria Curie-Sk³odowska University, Lublin, Poland Abstract In this paper the authors
More informationPlasma-Wall Interaction in the Open Divertor of Globus-M Spherical Tokamak
1 Plasma-Wall Interaction in the Open Divertor of Globus-M Spherical Tokamak V.K. Gusev 1), V.Kh. Alimov 2), I.I. Arkhipov 2), B.Ya. Ber 1), A.E. Gorodetsky 2), N.A. Khromov 1), A.A. Kurdumov 3), V.M.
More informationComparison of deuterium retention for ion-irradiated and neutronirradiated
13th International Workshop on Plasma-Facing Materials and Components for Fusion Applications / 1st International Conference on Fusion Energy Materials Science Comparison of deuterium retention for ion-irradiated
More informationChemical erosion of carbon based materials in fusion devices
Journal of Nuclear Materials 266±269 (1999) 51±57 Chemical erosion of carbon based materials in fusion devices Joachim Roth * Max-Planck-Institut fur Plasmaphysik, EURATOM Association, D-85748 Garching
More informationTRITIUM PRODUCTION IN PALLADIUM DEUTERIDE/HYDRIDE IN EVACUATED CHAMBER
Yamada, H., et al. Tritium Production in Palladium Deuteride/Hydride in Evacuated Chamber. in 8th International Conference on Cold Fusion. 2000. Lerici (La Spezia), Italy: Italian Physical Society, Bologna,
More informationDeuterium Inventory in Tore Supra : reconciling particle balance and post mortem analysis
Deuterium Inventory in Tore Supra : reconciling particle balance and post mortem analysis E. Tsitrone, C. Brosset, B. Pégourié, E. Gauthier, J. Bouvet, J. Bucalossi, S. Carpentier, Y. Corre, E. Delchambre,
More informationUse of a High-Resolution Overview Spectrometer for the Visible Range in the TEXTOR Boundary Plasma
Use of a High-Resolution Overview Spectrometer for the Visible Range in the TEXTOR Boundary Plasma Sebastijan BREZINSEK, Albrecht POSPIESZCZYK, Gennadij SERGIENKO, Philippe MERTENS and Ulrich SAMM Institut
More informationJET JET JET EFDA THE JOINT EUROPEAN TORUS A EUROPEAN SUCCESS STORY
EFDA LEAD ING DEVICE FOR FUSION STUDIES HOLDER OF THE WORLD RECORD OF FUSION POWER PRODUCTION EXPERIMENTS STRONGLY FOCUSSED ON THE PREPARATION FOR ITER EXPERIMENTAL DEVICE USED UNDER THE EUROPEAN FUSION
More informationMaterials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads
Mitglied der Helmholtz-Gemeinschaft Materials for Future Fusion Reactors under Severe Stationary and Transient Thermal Loads J. Linke, J. Du, N. Lemahieu, Th. Loewenhoff, G. Pintsuk, B. Spilker, T. Weber,
More informationPlasma and Fusion Research: Regular Articles Volume 10, (2015)
Possibility of Quasi-Steady-State Operation of Low-Temperature LHD-Type Deuterium-Deuterium (DD) Reactor Using Impurity Hole Phenomena DD Reactor Controlled by Solid Boron Pellets ) Tsuguhiro WATANABE
More informationProgress of experimental study on negative ion production and extraction
1 FIP/1-4 Progress of experimental study on negative ion production and extraction M. Kisaki 1, K. Tsumori 1,2,. Geng 2, K. Ikeda 1, H. akano 1,2, M. Osakabe 1,2, K. agaoka 1, Y. Takeiri 1,2 1 ational
More informationEXD/P3-13. Dependences of the divertor and midplane heat flux widths in NSTX
1 Dependences of the ertor and plane heat flux widths in NSTX T.K. Gray1,2), R. Maingi 2), A.G. McLean 2), V.A. Soukhanovskii 3) and J-W. Ahn 2) 1) Oak Ridge Institute for Science and Education (ORISE),
More informationThe fast-ion distribution function
The fast-ion distribution function Source Collisions Orbits RF Losses W. Heidbrink 3 MeV & 14.7 MeV protons Charge Exchange Reactivity σv Complex neutral beam sources are described by a few parameters
More informationThe Henryk Niewodniczański INSTITUTE OF NUCLEAR PHYSICS Polish Academy of Sciences ul. Radzikowskiego 152, Kraków, Poland
The Henryk Niewodniczański INSTITUTE OF NUCLEAR PHYSICS Polish Academy of Sciences ul. Radzikowskiego 152, 31-342 Kraków, Poland www.ifj.edu.pl/publ/reports/2014/ Kraków, 2014 Report No. 2068/AP Principles
More informationFlow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes
Flow measurements in the Scrape-Off Layer of Alcator C-Mod using Impurity Plumes S. Gangadhara,. Laombard M.I.T. Plasma Science and Fusion Center, 175 Albany St., Cambridge, MA 2139 USA Abstract Accurate
More informationITER Divertor Plasma Modelling with Consistent Core-Edge Parameters
CT/P-7 ITER Divertor Plasma Modelling with Consistent Core-Edge Parameters A. S. Kukushkin ), H. D. Pacher ), G. W. Pacher 3), G. Janeschitz ), D. Coster 5), A. Loarte 6), D. Reiter 7) ) ITER IT, Boltzmannstr.,
More informationThe FTU facilities. Regarding the the control and data acquisition system, last year we carried out the following activities:
The FTU facilities FTU Machine Summary of the machine operation During 2005, the machine operated at the high level of 91% of successful pulses. The experimental activity started in March and went on till
More informationDeuterium Balmer/Stark spectroscopy and impurity profiles: first results from mirror-link divertor spectroscopy system on the JET ITER-like wall
CCFE-PR(13)35 A.G. Meigs, S. Brezinsek, M. Clever, A. Huber, S. Marsen, C. Nicholas, M.Stamp, K-D Zastrow, and JET EFDA Contributors Deuterium Balmer/Stark spectroscopy and impurity profiles: first results
More informationPlasma-Wall Interaction Studies in the Full-W ASDEX Upgrade during Helium Plasma Discharges
1 EX/P6-21 Plasma-Wall Interaction Studies in the Full-W ASDEX Upgrade during Helium Plasma Discharges A. Hakola 1, S. Brezinsek 2, D. Douai 3, M. Balden 4, V. Bobkov 4, D. Carralero 4, H. Greuner 4, S.
More informationImproved EDGE2D-EIRENE Simulations of JET ITER-like Wall L-mode Discharges Utilising Poloidal VUV/visible Spectral Emission Profiles
CCFE-PR(15)26 K.D. Lawson, M. Groth, P. Belo, S. Brezinsek, G. Corrigan, A. Czarnecka, E. Delabie, P. Drewelow, D. Harting, I. KsiąŜek, C.F. Maggi, C. Marchetto, A.G. Meigs, S. Menmuir, M.F. Stamp, S.
More informationNSTX Plasma-Material Interface (PMI) Probe and supporting experiments
NSTX Plasma-Material Interface (PMI) Probe and supporting experiments J.P. Allain 1,2, C.N. Taylor 1, B. Heim 1,3 PPPL Collaborators: C.H. Skinner, H.W. Kugel, R. Kaita, A.L. Roquemore 1 Purdue University,
More informationScaling of divertor heat flux profile widths in DIII-D
1 Scaling of divertor heat flux profile widths in DIII-D C.J. Lasnier 1, M.A. Makowski 1, J.A. Boedo 2, N.H. Brooks 3, D.N. Hill 1, A.W. Leonard 3, and J.G. Watkins 4 e-mail:lasnier@llnl.gov 1 Lawrence
More informationA Project for High Fluence 14 MeV Neutron Source
A Project for High Fluence 14 MeV Neutron Source Mario Pillon 1, Maurizio Angelone 1, Aldo Pizzuto 1, Antonino Pietropaolo 1 1 Associazione ENEA-EURATOM Sulla Fusione, ENEA C.R. Frascati, via E. Fermi,
More informationMolecular dynamics simulations of C 2,C 2 H, C 2 H 2,C 2 H 3,C 2 H 4, C 2 H 5, and C 2 H 6 bombardment of diamond (111) surfaces
Available online at www.sciencedirect.com Journal of Nuclear Materials 375 (2008) 270 274 www.elsevier.com/locate/jnucmat Molecular dynamics simulations of C 2,C 2 H, C 2 H 2,C 2 H 3,C 2 H 4, C 2 H 5,
More informationSecondary ion mass spectrometry (SIMS)
Secondary ion mass spectrometry (SIMS) Lasse Vines 1 Secondary ion mass spectrometry O Zn 10000 O 2 Counts/sec 1000 100 Li Na K Cr ZnO 10 ZnO 2 1 0 20 40 60 80 100 Mass (AMU) 10 21 10 20 Si 07 Ge 0.3 Atomic
More informationSecondary Ion Mass Spectrometry (SIMS) Thomas Sky
1 Secondary Ion Mass Spectrometry (SIMS) Thomas Sky Depth (µm) 2 Characterization of solar cells 0,0 1E16 1E17 1E18 1E19 1E20 0,2 0,4 0,6 0,8 1,0 1,2 P Concentration (cm -3 ) Characterization Optimization
More informationProgress of Confinement Physics Study in Compact Helical System
1st IAEA Fusion Energy Conference Chengdu, China, 16-1 October, 6 IAEA-CN-149/ EX/5-5Rb Progress of Confinement Physics Study in Compact Helical System S. Okamura et al. NIFS-839 Oct. 6 1 EX/5-5Rb Progress
More informationImpact of Neon Injection on Electron Density Peaking in JET Hybrid Plasmas
1 P/233 Impact of Neon Injection on Electron Density Peaking in JET Hybrid Plasmas D. Frigione 1, M. Romanelli 2, C. Challis 2, J. Citrin 3, L. Frassinetti 4, J. Graves 5, J. Hobirk 6, F. Koechl 2, M.
More information