[1] Ch. Linsmeier, et al.. Material testing facilities and programs for plasma facing component testing. Nucl. Fusion, 2017, 57: 092012 .
[2] J. Linke , J. Compan , T. Hirai , G. Pintsuk , M. Rödig , and K. Wittlich , “Materials for nuclear energy systems ,” in Proceedings of Forum 2008 of the World Academy of Ceramics, Chianciano Terme, Italy, July 5–8, 2008 , Ceramic Materials in Energy Systems for Sustainable Development, edited by L. Gauckler (Techna Group Srl , 2009 ), pp. 307 –334 .
[3] Y. Ueda, et al.. Baseline high heat flux and plasma facing materials for fusion. Nucl. Fusion, 2017, 57: 092006 .
[4] P. T. Lang, et al.. ELM control strategies and tools: Status and potential for ITER. Nucl. Fusion, 2013, 53: 043004 .
[5] A. Loarte, et al.. Characteristics of type I ELM energy and particle losses in existing devices and their extrapolation to ITER. Plasma Phys. Controlled Fusion, 2003, 45: 1549 .
[6] M. Merola, et al.. Overview and status of ITER internal components. Fusion Eng. Des., 2014, 89: 890 .
[7] G. L. Kulcinski. First wall protection schemes for inertial confinement fusion reactors. J. Nucl. Mater., 1979, 85-86(1): 87-97 .
[8] V. Barabash, et al.. Armour materials for the ITER plasma facing components. Phys. Scr., 1999, T81: 74 .
[9] R. A. Pitts, et al.. A full tungsten divertor for ITER: Physics issues and design status. J. Nucl. Mater., 2013, 438: S48-S56 .
[10] T. E. Evans. ELM mitigation techniques. J. Nucl. Mater., 2013, 438: S11-S18 .
[11] T. Eich, et al.. Empirical scaling of inter-ELM power widths in ASDEX upgrade and JET. Nucl. Mater., 2013, 438: S72-S77 .
[12] K. Wang, et al.. Morphologies of tungsten nanotendrils grown under helium exposure. Sci. Rep., 2017, 7: 42315 .
[13] M. R. Gilbert and J.-C. Sublet , “Handbook of activation, transmutation, and radiation damage properties of the elements simulated using FISPACT-II & TENDL-2015; Magnetic fusion plants ,” Report No. CCFE-R(16)36, September 2016 .
[14] S. L. Dudarev, M. R. Gilbert, J.-Ch. Sublet. Spatial heterogeneity of tungsten transmutation in a fusion device. Nucl. Fusion, 2017, 57(4): 044002 .
[15] J. Linke , “Plasma facing materials and components for future fusion reactors ,” in Proceeding of the 12th Kudowa Summer School “Towards Fusion, to Energy,” Kudowa Zdroj , June 9–13, 2014 .
[16] R. Doerner, A. Hasegawa, M. Rieth, Y. Ueda, M. Wirtz. Behaviour of tungsten under irradiation and plasma interaction. J. Nucl. Mater., 2019, 519: 334-368 .
[17] I. Bobin-Vastra, S. Constans, P. Gavila, G. Pintsuk, B. Riccardi, M. Rödig. Qualification and post-mortem characterization of tungsten mock-ups exposed to cyclic high heat flux loading. Fusion Eng. Des., 2013, 88: 1858-1861 .
[18] R. A. Pitts et al. , J. Nucl. Mater. 415 (1 ), S957 –S964 (2011 ).
[19] Th. Loewenhoff, et al.. Impact of combined transient plasma/heat loads on tungsten performance below and above recrystallization temperature. Nucl. Fusion, 2015, 55: 123004 .
[20] J. P. Gunn, et al.. Surface heat loads on the ITER divertor vertical targets. Nucl. Fusion, 2017, 57: 046025 .
[21] J. Schlosser, et al.. Technologies for ITER divertor vertical target plasma facing components. Nucl. Fusion, 2005, 45(6): 512-518 .
[22] E. Visca, et al.. Hot radial pressing: An alternative technique for the manufacturing of plasma-facing components. Fusion Eng. Des., 2005, 75: 485-489 .
[23] A. Herrmann, et al.. Experiences with a solid tungsten divertor in ASDEX upgrade. Nucl. Mater. Energy, 2017, 12: 205-209 .
[24] C. Thomser, et al.. Plasma facing materials for the JET ITER-like wall. Fusion Sci. Technol., 2012, 62(1): 1-8 .
[25] T. Hirai, et al.. Use of tungsten material for the ITER divertor. Nucl. Mater. Energy, 2016, 9: 616-622 .
[26] A. R. Raffray et al. , Nucl. Fusion 54 , 033004 (2014 ).
[27] V. Barabash, F. Escourbiac, T. Hirai, J. Linke, Th. Loewenhoff, S. Panayotis, G. Pintsuk, I. Uytdenhouwen, M. Wirtz. Material properties and their influence on the behaviour of tungsten as plasma facing material. Nucl. Fusion, 2017, 57: 066018 .
[28] J. Du, J. Linke, Y. Ma, Z. Zhou. Fabrication and characterization of ultra-fine-grained tungsten by resistance sintering under ultra-high pressure. Mater. Sci. Eng., A, 2009, 505: 131-135 .
[29] Ch. Linsmeier, et al.. Development of advanced high heat flux and plasma-facing materials. Nucl. Fusion, 2017, 57: 092007 .
[30] J. W. Coenen, et al.. Materials for DEMO and reactor applications—Boundary conditions and new concepts. Phys. Scr., 2016, T167: 014002 .
[31] G. De Temmerman, T. Hirai, R. A. Pitts. The influence of plasma-surface interaction on the performance of tungsten at the ITER divertor vertical targets. Plasma Phys. Controlled Fusion, 2018, 60: 044018 .
[32] G. De Temmerman. High heat flux capabilities of the magnum-PSI linear plasma device. Fusion Eng. Des., 2013, 88: 483-487 .
[33] G. De Temmerman, R. P. Doerner, M. A. van den Berg, J. H. Yu. Study of temporal pulse shape effects on W using simulations and laser heating. Phys. Scr., 2016, T167: 014033 .
[34] J. Ahlf, et al.. The HFR Petten as a test bed for fusion materials and components. J. Nucl. Mater., 1994, 212-215(B): 1635-1639 .
[35] T. Hirai, et al.. ITER relevant high heat flux testing on plasma facing surfaces. Mater. Trans., 2005, 46(3): 412-424 .
[36] R. Duwe et al. , Fusion Technol. 1994 1995 , 355 –358 (1995 ).
[37] A. Schmidt et al. , Fusion Eng. Des. 83 (7-9 ), 1108 –1113 (2008 ).
[38] P. Majerus et al. , Fusion Eng. Des. 75-79 , 365 –369 (2005 ).
[39] G. Pintsuk. Tungsten as a plasma-facing material. Compr. Nucl. Mater., 2012, 4: 551-581 .
[40] A. Zhitlukhin, et al.. Effect of ELMS on ITER armour materials. J. Nucl. Mater., 2007, 363-365: 301-307 .
[41] B. Bazylev et al. , “Experimental validation of 3D simulations of tungsten melt erosion under ITER-like transient loads ,” in 18th International Conference on Plasma Surface Interactions in Controlled Fusion Devices , Toledo, Spain , May 26–30, 2008 .
[42] H. Greuner, et al.. Surface morphology changes of tungsten exposed to high heat loading with mixed hydrogen/helium beams. J. Nucl. Mater., 2014, 455: 681 .
[43] J. Linke, Th. Loewenhoff, G. Pintsuk, I. Uytdenhouwen, M. Wirtz. Thermal shock tests to qualify different tungsten grades as plasma facing material. Phys. Scr., 2016, T167: 014015 .
[44] M. Wirtz, et al.. Transient heat load challenges for plasma-facing materials during long-term operation. Nucl. Mater. Energy, 2017, 12: 148-155 .
[45] J. Linke, et al.. Performance of different tungsten grades under transient thermal loads. Nucl. Fusion, 2011, 51: 073017 .
[46] Th. Loewenhoff et al. , Phys. Scr. T145 , 014057 (2011 ).
[47] Th. Loewenhoff et al. , Fusion Eng. Des. 87 , 1201 –1205 (2012 ).
[48] K. Wittlich, et al.. Damage structure in divertor armor materials exposed to multiple ITER relevant ELM loads. Fusion Eng. Des., 2009, 84: 1982-1986 .
[49] J. Compan, T. Hirai, J. Linke, T. Renk. Reduction of preferential erosion of carbon fibre composites under intense transient heat pulses. Phys. Scr., 2007, T128: 246-249 .
[50] J. Linke. Plasma facing materials and components for future fusion devices-development, characterization and performance under fusion specific loading conditions. Phys. Scr., 2006, T123: 45-53 .
[51] J. Linke. High heat flux performance of plasma facing materials and components under service conditions in future fusion reactors. Trans. Fusion Sci. Technol., 2008, 53: 278-287 .
[52] M. Roedig et al. , J. Nucl. Mater. 417 , 761 –764 (2011 ).
[53] W. Kühnlein, J. Linke, G. Pintsuk, M. Rödig. Investigation of tungsten and beryllium behaviour under short transient events. Fusion Eng. Des., 2007, 82: 1720-1729 .
[54] B. Spilker et al. , Nucl. Mater. Energy 9 , 145 –152 (2016 ).
[55] B. Spilker, et al.. Experimental study of ELM-like heat loading on beryllium under ITER operational conditions. Phys. Scr., 2016, T167: 014024 .
[56] B. Spilker, et al.. High pulse number transient heat loads on beryllium. Nucl. Mater. Energy, 2017, 12: 1184-1188 .
[57] B. Spilker, et al.. Performance estimation of beryllium under ITER relevant transient thermal loads. Nucl. Mater. Energy, 2019, 18: 291-296 .
[58] A. Hassanein, I. Konkashbaev. Lifetime evaluation of plasma-facing materials during a tokamak disruption. J. Nucl. Mater., 1996, 233-237: 713-717 .
[59] Y. Igitkhanov, I. S. Landman, S. E. Pestchanyi, R. Pitts. Two-dimensional modeling of disruption mitigation by gas injection. Fusion Eng. Des., 2011, 86(9-11): 1616-1619 .
[60] G. Camus, G. Chevet, E. Martin, J. Schlosser. Damage modelling in plasma facing components. J. Nucl. Mater., 2009, 386-388: 747-750 .
[61] J. T. Busby, S. J. Zinkle. Structural materials for fission & fusion energy. Mater. Today, 2009, 12(11): 12-19 .
[62] M. J. Baldwin, R. P. Doerner, T. C. Lynch, J. H. Yu. Retention in tungsten resulting from extremely high fluence plasma exposure. Nucl. Mater. Energy, 2016, 9: 89-92 .
[63] A. Kreter, J. Linke, Th. Loewenhoff, G. Pintsuk, G. Sergienko, I. Steudel, B. Unterberg, E. Wessel, M. Wirtz. High pulse number thermal shock tests on tungsten with steady state particle background. Phys. Scr., 2017, T170: 014066 .
[64] T. Chraska, T. de Kruif, G. De Temmerman, J. Matejicek, T. W. Morgan, R. A. Pitts, G. G. van Eden, M. Wirtz, G. M. Wright. Effect of high-flux H/He plasma exposure on tungsten damage due to transient heat loads. J. Nucl. Mater., 2015, 463: 198-201 .
[65] A. Kreter, et al.. Linear plasma device PSI-2 for plasma-material interaction studies. Fusion Sci. Technol., 2015, 68: 8-14 .
[66] M. Wirtz et al. , Nucl. Mater. Energy 9 , 177 –180 (2016 ).
[67] A. Huber, et al.. Investigation of the impact of transient heat loads applied by laser irradiation on ITER-grade tungsten. Phys. Scr., 2014, T159: 014005 .
[68] G. Federici, et al.. Overview of the design approach and prioritization of R&D activities towards an EU DEMO. Fusion Eng. Des., 2016, 109-111: 1464-1474 .
[69] G. Pintsuk, et al.. High heat flux testing of first wall mock-ups with and without neutron irradiation. Nucl. Mater. Energy, 2016, 9: 41-45 .
[70] T. Tanabe. Radiation damage of graphite - degradation of material parameters and defect structures. Phys. Scr., 1996, T64: 7-16 .
[71] J. Linke, P. Lorenzetto, P. Majerus, M. Merola, D. Pitzer, M. Rödig. EU development of high heat flux components. Fusion Sci. Technol., 2005, 47(3): 678 .
[72] T. Hirai, J. Linke, M. Rödig, L. A. Singheiser. Performance of plasma-facing materials under intense thermal loads in tokamaks and stellarators. Fusion Sci. Technol., 2004, 46(1): 142-151 .