[1] TEXTOR special issue, Fusion Sci. Technol. 47 (2005).
[2] G.F. Federici, C.H. Skinner, J.N. Brooks, J.P. Coad, C. Grisolia, et al., Plasma e material interactions in current tokamaks and their implications for next step fusion devices, Nucl. Fusion 41 (2001) 1967.
[3] V. Philipps, T. Tanabe, Y. Ueda, A. Pospieszczyk, M.Z. Tokar, et al., Molybdenum test limiter experiments in TEXTOR, Nucl. Fusion 34 (1994) 1417.
[4] V. Philipps, A. Pospieszczyk, A. Huber, A. Kirschner, J. Rapp, et al., Experiments with tungsten limiters in TEXTOR-94, J. Nucl. Mater. 258-263 (1998) 858.
[5] G. Sergienko, B. Bazylev, T. Hirai, A. Huber, A. Kreter, et al., Experience with bulk tungsten test limiters under high heat loads: melting and melt layer propagation, Phys. Scr. T128 (2007) 81.
[6] A. Huber, V. Philipps, A. Pospieszczyk, M. Wada, M. Lehnen, et al., Comparison of impurity production, recycling and power deposition on carbon and tungsten limiters in TEXTOR-94, J. Nucl. Mater. 290-293 (2001) 276.
[7] V. Philipps, R. Neu, J. Rapp, U. Samm, M. Tokar, et al., Comparison of tokamak behaviour with tungsten and low-Z plasma facing materials, Plasma Phys. Control. Fusion 42 (2000) B283.
[8] J. Winter, Carbonization in tokamaks, J. Nucl. Mater. 145-147 (1987) 131.
[9] J. Winter, H.G. Esser, L. K€onen, V. Philipps, H. Reimer, et al., Boronization in TEXTOR, J. Nucl. Mater. 162-163 (1989) 713.
[10] J. Winter, H.G. Esser, G.L. Jackson, L. K€onen, A. Messiaen, et al., Improved plasma performance in TEXTOR with silicon coated surfaces, Phys. Rev. Lett. 71 (1993) 149.
[11] K.H. Finken, T. Eich, the dynamic ergodic divertor (DED) for TEXTOR-94 tokamak, Contrib. Plasma Phys. 40 (2000) 57.
[12] M. Lehnen, S.S. Abdullaev, G. Arnoux, S.A. Bozhenkov, M.W. Jakubowski, et al., Runaway generation during disruptions in JET and TEXTOR, J. Nucl. Mater. 390-391 (2009) 740.
[13] A. Kirschner, V. Philipps, J. Winter, U. K€ogler, Simulation of the plasma-wall interaction in a tokamak with the Monte Carlo code EROTEXTOR, Nucl. Fusion 40 (2000) 989.
[14] S. Brezinsek, G. Sergienko, A. Pospieszczyk, Ph. Mertens, U. Samm, et al., Characterization of the deuterium recycling flux in front of a graphite surface in the TEXTOR tokamak, Plasma Phys. Control. Fusion 47 (2005) 615.
[15] H.E. S€atherblom, M. Braun, B. Emmoth, J. Winter, J. Hilke, et al., A Computer-controlled particle collection and surface analysis system for tokamak scrape-off layer analysis, Nucl. Instr. Methods. A240 (1985) 151.
[16] B. Schweer, P. Wienhold, M. Rubel, B. Emmoth, R. Zag orski, et al., Fast reciprocating probe system for plasma edge characterization: construction and applications, in: Proc. 2nd German e Polish Conf. On Plasma Diagnostics, Greifswald, Germany, 2002.
[17] D. Nicolai, V. Borsuk, P. Drews, O. Grulke, K.P. Hollfeld, et al., A Multi-Purpose Manipulator system for W7-X as user facility for plasma edge investigation, in: 29th Symp. On Fusion Technology, P2.073, Prague, Czech Republic, 2016.
[18] T. Tanabe, V. Philipps, Y. Ueda, B. Unterberg, A. Pospieszczyk, et al., High Z limiter test in TEXTOR: impurity fluxes, thermal response and post-mortem analysis of a Mo limiter head“, J. Nucl. Mater. 212-215 (1994) 1370.
[19] Y. Ueda, T. Tanabe, V. Philipps, L. Koenen, A. Pospieszczyk, et al., Effects of impurities released from high Z test limiter on plasma performance in TEXTOR, J. Nucl. Mater. 220-222 (1995) 240.
[20] T. Tanabe, V. Philipps, Y. Ueda, B. Unterberg, A. Pospieszczyk, et al., High Z limiter test in TEXTOR, thermal response and post-mortem analysis, Fusion Eng. Des. 28 (1995) 13.
[21] M. Rubel, V. Philipps, U. K€ogler, T. Tanabe, D. Larsson, et al., Impact of molybdenum and tungsten limiters on impurity fluxes in the scrapeoff layer plasma of TEXTOR, J. Nucl. Mater. 249 (1997) 116.
[22] J. Rapp, M.Z. Tokar, L. K€onen, H.R. Koslowski, G. Bertschinger, et al., Transport studies of high-Z elements in neon edge radiation cooled discharges in TEXTOR-94, Plasma Phys. Control. Fusion 39 (1997) 1615.
[23] M. Wada, V. Philipps, A. Pospieszczyk, B. Unterberg, B. Schweer, et al., Impurity release from high-Z test limiters immersed in TEXTOR-94 edge plasmas, J. Nucl. Mater. 241-243 (1997) 799.
[24] T. Tanabe, V. Philipps, K. Nakamura, M. Fujine, Y. Ueda, et al., Examination of material performance of W exposed to high heat load, J. Nucl. Mater. 241-243 (1997) 1164.
[25] M. Wada, T. Tanabe, V. Philipps, B. Unterberg, A. Pospieszczyk, et al., High heat flux exposure experiments of a tungsten test limiter at TEXTOR-94, J. Nucl. Mater. 258-263 (1998) 853.
[26] M. Rubel, V. Philipps, A. Huber, T. Tanabe, Formation of carbon containing layers on tungsten test limiters, Phys. Scr. T81 (1999) 61.
[27] T. Tanabea, T. Ohgob, M. Wadac, M. Rubeld, V. Philipps, et al., Material mixing on W/C twin limiter in TEXTOR-94, Fusion Eng. Des. 49 & 50 (2000) 355.
[28] T. Tanabe, M. Wada, T. Ohgo, V. Philipps, M. Rubel, et al., Application of tungsten for plasma limiters in TEXTOR, J. Nucl. Mater. 283-287 (2000) 1128.
[29] M. Rubel, T. Tanabe, V. Philipps, B. Emmoth, A. Kirschner, et al., Graphite-tungsten twin limiters in studies of material mixing on high heat flux components, J. Nucl. Mater. 283-287 (2000) 1089.
[30] M. Wada, T. Ohgo, A. Pospieszczyk, A. Huber, G. Sergienko, et al., Local emission and core concentration of tungsten in TEXTOR-94 plasmas operated with tungsten test limiter and poloidal limiters, J. Nucl. Mater. 290-293 (2001) 768.
[31] K. Ohya, R. Kawakami, T. Tanabe, M.Wada, T. Ohgo, et al., Simulation study of carbon and tungsten deposition on W/C twin test limiter, J. Nucl. Mater. 283-287 (2000) 1182.
[32] K. Ohya, R. Kawakami, T. Tanabe, M.Wada, T. Ohgo, et al., Simulation calculations on of mutual contamination between tungsten and carbon and its impact on plasma surface interactions, J. Nucl. Mater. 290-293 (2001) 303.
[33] K. Ohya, J. Kawata, T. Tanabe, M. Wada, Y. Ueda, et al., Ion reflection and sputtering at tungsten surface exposed to edge plasmas in TEXTOR, J. Nucl. Mater. 258-263 (1998) 1055.
[34] K. Ohya, J. Kawata, T. Tanabe, M. Wada, T. Ohgo, et al., Particle emission from a tungsten test limiter in TEXTOR-94: a comparison between experimental and Monte Carlo simulated results, J. Nucl. Mater. 266-269 (1999) 629.
[35] K. Ohya, T. Tanabe, M. Wada, T. Ohgo, V. Philipps, et al., Simulation and experimental studies of impurity release from tungsten exposed to edge plasmas in TEXTOR, Nucl. Instr. Methods B153 (1999) 354.
[36] K. Ohya, T. Hirai, T. Tanabe, M. Wada, T. Ohgo, et al., Simulation of hydrogen and hydrocarbon release from W-Ta and W-C twin test limiters in TEXTOR edge plasmas, J. Nucl. Mater. 313-316 (2003) 571.
[37] M. Rubel, V. Philipps, A. Pospieszczyk, T. Tanabe, S. K€otterl, An overview of fuel inventory in tungsten and composite limiters, J. Nucl. Mater. 307-311 (2002) 111.
[38] T. Hirai, V. Philipps, T. Tanabe, M. Wada, A. Huber, et al., Hydrogen recycling and microstructures of tantalum and tungsten twin limiters exposed in TEXTOR-94, J. Nucl. Mater. 307-311 (2002) 79.
[39] T. Hirai, M. Rubel, V. Philipps, A. Huber, T. Tanabe, et al., Testing of tungsten and tantalum limiters at the TEXTOR tokamak: material performance and deuterium retention, Phys. Scr. T103 (2003) 59.
[40] T. Ohgo, M. Wada, A. Pospieszczyk, W. Biel, K. Kondo, et al., Heat load to a tantalum-tungsten twin-test-limiter and the effect to high-Z core plasma concentration of TEXTOR-94, J. Nucl. Mater. 307-311 (2002) 149.
[41] M. Wada, T. Hirai, T. Ohgo, T. Tanabe, K. Ohya, et al., Inhomogeneous heat loading to high-Z test limiters depending upon the limiter materials, J. Nucl. Mater. 313-316 (2003) 292.
[42] T. Ohgo, M. Wada, K. Ohya, T. Hirai, W. Biel, et al., Effect upon the core plasma radiation due to high power laser injection onto C, W and Ta test limiters in TEXTOR, J. Nucl. Mater. 313-316 (2003) 1156.
[43] T. Hirai, V. Philipps, A. Huber, G. Sergienko, J. Linke, et al., Performance and erosion of a tungsten brush limiter tested at the TEXTOR tokamak, J. Nucl. Mater. 313-316 (2003) 69.
[44] A. Huber, M. Mayer, V. Philipps, A. Pospieszczyk, T. Ohgo, et al., Insitu measurements of trapped hydrogen by laser desorption in TEXTOR- 94, Phys. Scr. T94 (2001) 102.
[45] A. Huber, V. Philipps, T. Hirai, A. Kirschner, M. Lehnen, et al., Behaviour of silicon doped CFC limiter under high heat load in TEXTOR, Phys. Scr. T91 (2001) 61.
[46] P. Mertens, M. Silz, Most recent results from laser-induced fluorescence on TEXTOR 94: atomic silicon, in: Proc. 7th Symp. Laser-aided Plasma Diag. LAPD-7, Fukuoka, 1995, p. 150.
[47] A. Huber, I. Beigman, D. Borodin, Ph. Mertens, V. Philipps, et al., Spectroscopic observation of Si I- and Si II emission lines in the boundary of TEXTOR and comparison with kinetic calculations, Plasma Phys. Control. Fusion 45 (2003) 89.
[48] A. Pospieszczyk, V. Philipps, E. Casarotto, U. K€ogler, B. Schweer, et al., Chemical erosion measurements from various carbon based limiters and coatings in TEXTOR, J. Nucl. Mater. 241-243 (1997) 883.
[49] A. Pospieszczyk, B. Schweer, V. Philipps, A. Huber, G. Sergienko, et al., B4C-limiter experiments at TEXTOR, J. Nucl. Mater. 313-316 (2003) 223.
[50] M. Laux, W. Schneider, P. Wienhold, B. Ju¨ttner, A. Huber, et al., Arcing at B4C-covered limiters exposed to a SOL plasma, J. Nucl. Mater. 313-316 (2003) 64.
[51] S. K€otterl, H. Bolt, H. Greuner, A. Huber, J. Linke, et al., Development of thick B4C coatings for the first wall of W7-X, Phys. Scr. T91 (2001) 117.
[52] H.G. Esser, J. Winter, V. Philipps, A. Pospieszczyk, J. von Seggern, et al., Protection of limiter surfaces by films locally deposited during TEXTOR discharges, J. Nucl. Mater. 220-222 (1995) 457.
[53] P. Wienhold, H.G. Esser, D. Hildebrandt, A. Kirschner, M. Mayer, et al., Investigation of carbon transport in the scrape-off layer of TEXTOR-94, J. Nucl. Mater. 290-293 (2001) 362.
[54] A. Kirschner, A. Huber, V. Philipps, A. Pospieszczyk, P. Wienhold, et al., Modelling of erosion and deposition at limiter surfaces and divertor target plates, J. Nucl. Mater. 290-293 (2001) 238.
[55] P. Wienhold, V. Philipps, A. Kirschner, A. Huber, J. von Seggern, et al., Short and long range transport of materials eroded from wall components in fusion devices, J. Nucl. Mater. 313-316 (2003) 313.
[56] M. Rubel, P. Wienhold, D. Hildebrandt, Ion beam analysis methods in studies of plasma facing materials in controlled fusion devices, Vacuum 70 (2003) 423.
[57] V. Philipps, A. Pospieszczyk, H.G. Esser, U. K€ogler, G. Mank, et al., Impurity release and deposition processes close to limiter surfaces in TEXTOR, J. Nucl. Mater. 241-243 (1997) 105.
[58] M. Rubel, J. Coenen, D. Ivanova, S. M€oller, P. Petersson, et al., Tungsten migration studies by controlled injection of volatile compounds, J. Nucl. Mater. 438 (2013) S170.
[59] M. Rubel, A. Weckmann, P. Str€om, P. Petersson, A. Garcia-Carrasco, et al., Tracer techniques for the assessment of material migration and surface modification of plasma facing components, J. Nucl. Mater. 463 (2015) 280.
[60] A. Weckmann, P. Petersson, M. Rubel, P. Wienhold, S. Brezinsek, et al., Local migration studies of high-Z metals in the TEXTOR tokamak, Phys. Scr. T167 (2016) 014058.
[61] A. Pospieszczyk, T. Tanabe, V. Philipps, G. Sergienko, T. Ohgo, et al., Operation of TEXTOR with tungsten poloidal main limiters, J. Nucl. Mater. 290-293 (2013) S170.
[62] G. Sergienko, B. Bazylev, A. Huber, A. Kreter, A. Litnovsky, et al., Erosion of tungsten limiter under high-heat flux in TEXTOR“, J. Nucl. Mater. 363-365 (2001) 947.
[63] M.J. Rubel, G. Sergienko, A. Kreter, A. Pospieszczyk, M. Psoda, et al., An overview of fuel retention and morphology in a castellated tungsten limiter, Fusion Eng. Des. 83 (2008) 1049.
[64] T. Hirai, E. Bondarchuk, A.I. Borovkov, th. Koppitz, J. Linke, et al., Development and testing of a bulk tungsten tile for the JET divertor, Phys. Scr. T128 (2007) 144.
[65] M. Psoda, M. Rubel, G. Sergienko, P. Sundelin, A. Pospieszczyk, Material mixing on plasma-facing components: compound formation, J. Nucl. Mater. 386-388 (2009) 740.
[66] A. Litnovsky, V. Philipps, P. Wienhold, A. Kreter, A. Kirschner, et al., Overview of material migration and mixing, fuel retention and cleaning of ITER-like castellated structures in TEXTOR, J. Nucl. Mater. 415 (2011) S289.
[67] D. Matveev, A. Kirschner, A. Litnovsky, M. Komm, D. Borodin, et al., Modelling of impurity deposition in gaps of castellated surfaces with the 3D-GAPS code, Plasma Phys. Contr. Fusion 52 (2010) 075007.
[68] K. Ohya, T. Tanabe, M. Rubel, M. Wada, T. Ohgo, et al., Modelling of erosion and deposition patterns on CeW and WeTa twin limiters exposed to the TEXTOR edge plasmas, J. Nucl. Mater. 329-333 (2004) 732.
[69] V. Philipps, D. Kogut, H.G. Esser, G. Sergienko, M. Zlobinski, et al., Deposition and qualification of tungsten coatings produced by plasma deposition in WF6 precursor gas, Phys. Scr. T145 (2011) 014030.
[70] A. Kirschner, P. Wienhold, V. Philipps, J.P. Coad, A. Huber, et al., Modelling of carbon transport and re-deposition in fusion devices:evidence of enhanced re-erosion of in-situ deposited carbon films, J. Nucl. Mater. 328 (2004) 62.
[71] A. Kirschner, A. Kreter, P. Wienhold, S. Brezinsek, J.W. Coenen, et al., Deposition and re-erosion studies by means of local impurity injection in TEXTOR, J. Nucl. Mater. 415 (2011) S239.
[72] A. Kirschner, P. Wienhold, D. Borodin, C. Bj€orkas, O. Van Hoey, et al., Studies of impurity migration in TEXTOR by local tracer injection, J. Nucl. Mater. 438 (2013) S723.
[73] D. Naujoks, R. Behrisch, Erosion and re-deposition at the vessel walls in fusion devices, J. Nucl. Mater. 220-222 (1995) 227.
[74] M.J. Rubel, J.P. Coad, K. Stenstr€om, P. Wienhold, J. Likonen, et al., Overview of tracer techniques in studies of material erosion, redeposition and fuel inventory in tokamaks, J. Nucl. Mater. 329-333 (2004) 795.
[75] J.P. Coad, J. Likonen, M. Rubel, E. Vainonen-Ahlgren, D.E. Hole, et al., Overview of material re-deposition and fuel retention studies at JET with the Gas Box divertor, Nucl. Fusion 46 (2006) 350.
[76] S.L. Allen, W.R. Wampler, A.G. McLean, D.G. Whyte, W.P. West, et al., 13C transport studies in L-mode divertor plasmas on DIII-D, J. Nucl. Mater. 337-339 (2005) 30.
[77] R. Pugno, K. Krieger, M. Airila, L. Aho-Mantila, A. Kreter, et al., Investigation of local carbon transport in the ASDEX Upgrade divertor using 13CH4 puffing, J. Nucl. Mater. 390-391 (2009) 68.
[78] P. Petersson, M. Rubel, G. Possnert, S. Brezinsek, B. Pegourie, Nuclear reaction and heavy ion ERD analysis of wall materials from controlled fusion devices: deuterium and nitrogen-15 studies, Nucl. Instr. Methods B273 (2012) 113.
[79] P. Petersson, M. Rubel, G. Possnert, S. Brezinsek, A. Kreter, et al., Overview of nitrogen-15 application as a tracer gas for material migration and retention studies in tokamaks, Phys. Scr. T159 (2014) 014042.
[80] P. Petersson, A. Hakola, J. Likonen, M. Mayer, J. Miettunen, et al., Injection of nitrogen-15 tracer into ASDEX-Upgrade: new technique in material migration studies, J. Nucl. Mater. 438 (2013) S616.
[81] D. Ivanova, M. Rubel, V. Philipps, B. Schweer, M. Freisinger, et al., Laser-based and thermal methods for fuel removal and cleaning of plasma-facing components, J. Nucl. Mater. 415 (2001) S801.
[82] P. Wienhold, F. Weschenfelder, J. Winter, Colorimetric measurements of carbon erosion and deposition on extended areas of plasma facing components in TEXTOR, J. Nucl. Mater. 220-222 (1995) 452.
[83] P. Wienhold, F. Weschenfelder, Two-dimensional measurements of thin film erosion and deposition by colorimetry of interference colours and its application in fusion devices, Vacuum 47 (1996) 919.
[84] M.J. Rubel, J.P. Coad, G.F. Neill, C.Walker, P. Wienhold, et al., Erosion and re-deposition on diagnostic mirrors for ITER: first mirror test at JET and TEXTOR, in: Proc. 30th EPS Conf. On Plasma Physics and Controlled Fusion, Europhys. Conf. Abstracts 27A, 2003.
[85] P. Wienhold, A. Litnovsky, V. Philipps, B. Schweer, G. Sergienko, et al., Exposure of metal mirrors in the scrape-off layer of TEXTOR, J. Nucl. Mater. 337-339 (2005) 1116.
[86] A. Litnovsky, P. Wienhold, V. Philipps, A. Romanyuk, O. Schmitz, et al., Diagnostic mirrors for ITER: a material choice and the impact of erosion and deposition on their performance, J. Nucl. Mater. 363-365 (2007) 1395.
[87] D. Larsson, M. Rubel, Ion flux measurements with the improved collector probe system at the TEXTOR-94 tokamak, Rev. Sci. Instr. 69 (1998) 2671.
[88] M. Rubel, F. Waelbroeck, H. Bergs ker, P. Wienhold, B. Emmoth, et al., Oxygen impurity analysis by collector probe measurements in the carbonised TEXTOR tokamak, J. Nucl. Mater. 161 (1989) 153.
[89] B. Emmoth, M. Rubel, P. Wienhold, J. Winter, H. Bergs ker, Metal impurity fluxes in the TEXTOR scrape-off layer measured by collector probes in the presence of ALT-II toroidal belt limiter, J. Nucl. Mater. 162-164 (1989) 409.
[90] P. Wienhold, J. Von Seggern, H.G. Esser, J. Winter, H. Bergs ker, et al., Impurity redeposition in the SOL of TEXTOR after boronization, J. Nucl. Mater. 176-177 (1990) 150.
[91] I. Gudowska, H. Bergs ker, B. Emmoth, P. Wienhold, M. Rubel, Fluxes of boron in the scrape-off plasma of TEXTOR following boronization, J. Nucl. Mater. 176-177 (1990) 363.
[92] P. Wienhold, J. Von Seggern, Oxygen gettering on graphite in the SOL of TEXTOR after wall conditioning with boron, Vacuum 43 (1992) 745.
[93] M. Rubel, P. Wienhold, N. Almqvist, B. Emmoth, H.G. Esser, et al., Silicon fluxes in the scrape-off layer plasma during silicon-assisted operation of TEXTOR, J. Nucl. Mater. 220-222 (1995) 536.
[94] M. Rubel, H. Bergs ker, B. Emmoth, P. Wienhold, F. Waelbroeck, et al., Deuterium and impurity fluxes in the TEXTOR scrape-off layer measured at different limiter configurations, Phys. Scr. 43 (1991) 508.
[95] M. Rubel, V. Philipps, U. K€ogler, T. Tanabe, D. Larsson, et al., Impact on molybdenum and tungsten test limiters on ion fluxes in the plasma edge of TEXTOR, J. Nucl. Mater. 249 (1997) 116.
[96] M. Rack, Y. Liang, H. Jaegers, J. A mann, G. Satheeswaran, et al., A rotating directional probe for the measurements of fast ion losses and plasma rotation at Tokamak Experiment for Technology Oriented Research, Rev. Sci. Instrum. 84 (2013) 083501.
[97] Y. Yang, Y. Liang, Y. Sun, T. Zhang, J. Pearson, et al., Experimental observations of plasma edge magnetic field response to resonant magnetic perturbation on the TEXTOR tokamak, Nucl. Fusion 52 (2012) 074014.
[98] Y. Xu, C. Hidalgo, I. Shesterikov, M. Berte, P. Dumortier, et al., Role of symmetry-breaking induced by Er B shear flows on developing residual stresses and intrinsic rotation in the TEXTOR tokamak, Nucl. Fusion 53 (2013) 072001.
[99] K. Wongrach, K.H. Finken, S.S. Abdullaev, O. Willi, L. Zeng, et al., Runaway electron studies in TEXTOR, Nucl. Fusion 55 (2015) 053008.
[100] B. Emmoth, A. Kreter, A. Hall en, M. Jakubowski, M. Lehnen, et al., Insitu measurements of carbon and deuterium deposition using the fast reciprocating probe in TEXTOR, J. Nucl. Mater. 390-391 (2009) 179.
[101] N. Almqvist, M. Rubel, S. Fredriksson, B. Emmoth, P. Wienhold, et al., AFM and STM characterization of surfaces exposed to high flux deuterium plasma, J. Nucl. Mater. 220-222 (1995) 917.
[102] N. Almqvist, M. Rubel, P. Wienhold, S. Fredriksson, Roughness determination of plasma-modified surface layers with atomic force microscopy, thin Solid Films 270 (1995) 426.
[103] S. Muto, T. Tanabe, A. Hirota, M. Rubel, V. Philipps, et al., TEM and EELS characterization of carbon dust and co-deposited layers from the TEXTOR tokamak, J. Nucl. Mater. 307-311 (2002) 1289.
[104] M. Rubel, J. von Seggern, P. Karduck, V. Philipps, A. Vevecka-Priftaj, et al., Analysis and oxidation of thick deposits on TEXTOR plasmafacing components, J. Nucl. Mater. 196-199 (1999) 1185.
[105] M. Rubel, G. De Temmerman, G. Sergienko, P. Sundelin, B. Emmoth, et al., Fuel removal from plasma-facing components by oxidation-based techniques. An overview of surface conditions after oxidation, J. Nucl. Mater. 363-365 (2007) 877.
[106] M. Rubel, Analysis of plasma-facing materials: material migration and fuel retention, Phys. Scr. T123 (2006) 55.
[107] M. Rubel, J.P. Coad, J. Likonen, V. Philipps, Analysis of fuel retention in plasma-facing components from controlled fusion devices, Nucl. Instr. Methods B267 (2009) 711.
[108] M. Rubel, E. Fortuna, A. Kreter, E. Wessel, V. Philipps, et al., Overview of comprehensive characterization of erosion zones on plasma facing components, Fusion Eng. Des. 81 (2006) 211.
[109] M. Rubel, M. Cecconello, Ja Malmberg, G. Sergienko, W. Biel, et al., Dust particles in controlled fusion devices: morphology, observations in the plasma and influence on the plasma performance, Nucl. Fusion 41 (2001) 1087.
[110] E. Fortuna, M. Rubel, M. Psoda, M. Andrzejczuk, K.J. Kurzydowski, et al., Plasma induced damage of tungsten coatings on graphite limiters, Phys. Scr. T128 (2007) 162.
[111] E. Fortunazale sna, A. Weckmann, J. Grzonka, M. Rubel, H.G. Esser, et al., Dust survey following the final shutdown of TEXTOR: metal particles and fuel retention, Phys. Scr. T167 (2016) 014059.
[112] J. Grzonka, L. Ciupinski, J. Smalckoziorowska, O.V. Ogorodnikova, M. Mayer, et al., Electron microscopy observation of radiation damage in irradiated and annealed tungsten, Nucl. Instr. Methods B340 (2014) 27.
[113] A. Garciacarrasco, P. Petersson, A. Hallen, J. Grzonka, M.R. Gilbert, et al., Impact of helium implantation and ion-induced damage on reflectivity of molybdenum mirrors, Nucl. Instr. Methods B382 (2016) 91.
[114] A. Baronwiechec, E. Fortunazale sna, J. Grzonka, M. Rubel, A. Widdowson, et al., First dust study in JET with the ITER-like wall: sampling, analysis and classification, Nucl. Fusion 55 (2015) 113033.
[115] J.W. Mayer, E. Rimini, Ion Beam Handbook for Material Analysis, Academic Press, New York, 1977.
[116] J.R. Tesmer, M. Nastasi (Eds.), Handbook of Modern Ion Beam Analysis, Materials Research Society, Pittsburg, USA, 1995.
[117] M. Mayer, E. Gauthier, K. Sugiyama, U. Von Toussaint, Quantitative depth profiling of deuterium up to very large depths, Nucl. Instr. Methods B267 (2009) 506.
[118] P. Strom, P. Petersson, M. Rubel, G. Possnert, A combined segmented anode gas ionization chamber and time-of-flight detector for heavy ion elastic recoil detection analysis, Rev. Sci. Instrum. 87 (2016) 103303.
[119] P. Petersson, A. Kreter, G. Possnert, M. Rubel, Nuclear micro-beam analysis of deuterium distribution in carbon fibre composites for controlled fusion devices, Nucl. Instr. Methods B268 (2010) 1833.
[120] P. Petersson, M. Rubel, G. Possnert, B. Pegourie, Micro-distribution of fuel and metal in carbon-based plasma-facing materials, Phys. Scr. T145 (2012) 014014.
[121] H. Bergsaker, I. Bykov, P. Petersson, G. Possnert, J. Likonen, et al., Microstructure and inhomogeneous fuel trapping at divertor surfaces in the JET tokamak, Nucl. Instr. Methods B332 (2014) 266.
[122] A.G. Carrasco, S. Moller, P. Petersson, D. Ivanova, A. Kreter, et al., Impact of ion cyclotron wall conditioning on fuel removal from plasmafacing components at TEXTOR, Phys. Scr. T159 (2014) 014017.
[123] A.G. Carrasco, T. Wauters, P. Petersson, A. Drenik, M. Rubel, et al., Nitrogen removal from plasma-facing components by ion cyclotron wall conditioning in TEXTOR, J. Nucl. Mater. 463 (2015) 688.
[124] R. Neu, V. Bobkov, R. Dux, J. Fuchs, O. Gruber, et al., Ten years of W program in ASDEX upgrade-challenges and conclusions, Phys. Scr. T138 (2009) 014038.
[125] R. Neu, A. Kallenbach, M. Balden, V. Bobkov, J.W. Coenen, et al., Overview on plasma operation with a full tungsten wall in ASDEX Upgrade, J. Nucl. Mater. 438 (2013) S34.
[126] J. Linke, F. Escourbiac, I.V. Mazul, R.E. Nygren, M. Rodig, et al., High heat flux testing of plasma facing materials and components e status and perspectives for ITER related activities, J. Nucl. Mater. 367-370 (2007) 1422.
[127] J. Linke, Plasma facing materials and components for future fusion devicesddevelopment, characterization and performance under fusion specific loading conditions, Phys. Scr. T123 (2006) 45.
[128] J. Roth, E. Tsitrone, A. Loarte, T. Loarer, G.F. Counsell, et al., Recent analysis of key plasma wall interactions issues for ITER, J. Nucl. Mater. 390-391 (2009) 1.
[129] G.F. Matthews, P. Edwards, T. Hirai, M. Kear, A. Lioure, et al., Overview of the ITER-like wall project, Phys. Scr. T128 (2007) 137.
[130] G.F. Matthews, P. Edwards, H. Greuner, A. Loving, H. Maier, et al., Current status of the JET ITER-like wall project, Phys. Scr. T138 (2009) 014030.
[131] G.F. Matthews, M. Beurskens, S. Brezinsek, M. Groth, E. Joffrin, et al., JET ITER-Like wall e overview and experimental program, Phys. Scr. T145 (2012) 014001.
[132] G.F. Matthews, JET-EFDAContributors,ASDEX-Upgrade Team,”Plasma operation with an all metal first-wall: comparison of an ITER-like wall with a carbon wall in JET, J. Nucl. Mater. 438 (2013) S2.
[133] S. Brezinsek, A. Widdowson, M. Mayer, V. Philipps, P. Baronwiechec, et al., Beryllium migration in JET ITER-like wall plasmas, Nucl. Fusion 55 (2015) 063021.
[134] T. Loarer, S. Brezinsek, V. Philipps, J. Bucalossi, D. Douai, et al., Comparison of long term fuel retention in JET between carbon and the ITER-like wall, J. Nucl. Mater. 438 (2013) S108.
[135] R.A. Pitts, S. Carpentier, F. Escourbiac, T. Hirai, V. Komarov, et al., A Full tungsten divertor for ITER: physics issues and design status, J. Nucl. Mater. 438 (2013) S48.
[136] Ph. Mertens, O. Neubauer, V. Philipps, S. Ciattaglia, A. Huber, et al., Removable samples for ITER: feasibility and conceptual study, Phys. Scr. T159 (2014) 014004.