6.4 Summary
111
In the last half of this chapter, damaging and degradation of Carbon and Tungsten
(W) are separately introduced with consideration of their influence on hydrogen recycling. Li and Be are briefly summarized as PFM. Although structure materials like
stainless steels should not be used as PFM, hydrogen recycling could be influenced
by those materials used as heat sink of PFM.
It should be mentioned again that PMI is a critical scientific issue for establishment
of a fusion reactor as a power source, with major potential limitations on plasma core
and edge operating parameters. Gaining understanding and predictive capability in
this area will require simultaneously addressing complex and diverse physics and
chemistry occurring over a wide range of lengths (angstroms to meters) and times
(femtoseconds to days).
References
1. J. Linke, T. Hirai, M. Rödig et al., Performance of plasma-facing materials under intense
thermal load in tokamaks and stellarators. Fusion Sci. Technol. 46, 142–151 (2004)
2. N. Asakura, K. Hoshino, S. Suzuki et al., Studies of power exhaust and divertor design for a
1.5 GW-level fusion power DEMO. Nucl. Fusion 57, 126050 (2017)
3. R. Wenninger, R. Albanese, R. Ambrosino et al., The DEMO wall load challenge. Nucl. Fusion
57, 046002 (2017)
4. V. Barabash, G. Federici, J. Linke et al., Material/plasma surface interaction issues following
neutron damage. J. Nucl. Mater. 313–316, 42–51 (2003)
5. Yu.F. Baranov, C.D. Challis, J. Ongena et al., Large ELM-like events triggered by core MHD
in JET advanced tokamak plasmas: impact on plasmas profiles, plasma-facing components and
heating systems. Nucl. Fusion 52(14), 023018 (2012)
6. R.A. Pitts, G. Arnoux, M. Beurskens et al., The impact of large ELMs on JET. J. Nucl. Mater.
390–391, 755–759 (2009)
7. A. Huber, G. Arnoux, M.N.A. Beurskens, Radiation loads onto plasma-facing components of
JET during transient events–experimental results and implications for ITER. J. Nucl. Mater.
415, S821–S827 (2011)
8. V. Rohde, M. Balden, the ASDEX Upgrade Team, Arc erosion of full metal plasma facing
components at the inner baffle region of ASDEX Upgrade. Nucl. Mater. Energy 9, 36–39
(2016)
9. H. Timko, F.F. Djurabekova, K. Nordlund et al., Mechanism of surface modification in the
plasma-surface interaction in electrical arcs. Phys. Rev. B 81, 184109 (2010)
10. D.L. Rudakova, C.P. Chrobak, R.P. Doerner et al., Arcing and its role in PFC erosion and dust
production in DIII-D. J. Nucl. Mater. 438, S805–S808 (2013)
11. T.E. Evans, ELM mitigation techniques. J. Nucl. Mater. 438, S11–S18 (2013)
12. A.H. Boozer, Runaway electrons and ITER. Nucl. Fusion 57(14), 056018 (2017)
13. A. Kreter, Reactor-relevant plasma-material interaction studies in linear plasma devices. Fusion
Sci. Technol. 59, 51–56 (2011)
14. J.W. Coenen, G. Arnoux, B. Bazylev et al., ELM induced tungsten melting and its impact on
tokamak operation. J. Nucl. Mater. 463, 78–84 (2015)
15. G. Sergienko, B. Bazylev, T. Hirai, Experience with bulk tungsten test-limiters under high heat
loads: melting and melt layer propagation. Phys. Scr. T128, 81–86 (2007)
16. T. Tanabe, V. Philipps, B. Unterberg et al., High Z limiter test in TEXTOR. J. Nucl. Mater.
212–215, 1370–1378 (1994)
17. T. Tanabe, M. Fujine, H. Noguchi et al., High heat load test of molybdenum. J. Nucl. Mater.
200, 120–127 (1993)
111
In the last half of this chapter, damaging and degradation of Carbon and Tungsten
(W) are separately introduced with consideration of their influence on hydrogen recycling. Li and Be are briefly summarized as PFM. Although structure materials like
stainless steels should not be used as PFM, hydrogen recycling could be influenced
by those materials used as heat sink of PFM.
It should be mentioned again that PMI is a critical scientific issue for establishment
of a fusion reactor as a power source, with major potential limitations on plasma core
and edge operating parameters. Gaining understanding and predictive capability in
this area will require simultaneously addressing complex and diverse physics and
chemistry occurring over a wide range of lengths (angstroms to meters) and times
(femtoseconds to days).
References
1. J. Linke, T. Hirai, M. Rödig et al., Performance of plasma-facing materials under intense
thermal load in tokamaks and stellarators. Fusion Sci. Technol. 46, 142–151 (2004)
2. N. Asakura, K. Hoshino, S. Suzuki et al., Studies of power exhaust and divertor design for a
1.5 GW-level fusion power DEMO. Nucl. Fusion 57, 126050 (2017)
3. R. Wenninger, R. Albanese, R. Ambrosino et al., The DEMO wall load challenge. Nucl. Fusion
57, 046002 (2017)
4. V. Barabash, G. Federici, J. Linke et al., Material/plasma surface interaction issues following
neutron damage. J. Nucl. Mater. 313–316, 42–51 (2003)
5. Yu.F. Baranov, C.D. Challis, J. Ongena et al., Large ELM-like events triggered by core MHD
in JET advanced tokamak plasmas: impact on plasmas profiles, plasma-facing components and
heating systems. Nucl. Fusion 52(14), 023018 (2012)
6. R.A. Pitts, G. Arnoux, M. Beurskens et al., The impact of large ELMs on JET. J. Nucl. Mater.
390–391, 755–759 (2009)
7. A. Huber, G. Arnoux, M.N.A. Beurskens, Radiation loads onto plasma-facing components of
JET during transient events–experimental results and implications for ITER. J. Nucl. Mater.
415, S821–S827 (2011)
8. V. Rohde, M. Balden, the ASDEX Upgrade Team, Arc erosion of full metal plasma facing
components at the inner baffle region of ASDEX Upgrade. Nucl. Mater. Energy 9, 36–39
(2016)
9. H. Timko, F.F. Djurabekova, K. Nordlund et al., Mechanism of surface modification in the
plasma-surface interaction in electrical arcs. Phys. Rev. B 81, 184109 (2010)
10. D.L. Rudakova, C.P. Chrobak, R.P. Doerner et al., Arcing and its role in PFC erosion and dust
production in DIII-D. J. Nucl. Mater. 438, S805–S808 (2013)
11. T.E. Evans, ELM mitigation techniques. J. Nucl. Mater. 438, S11–S18 (2013)
12. A.H. Boozer, Runaway electrons and ITER. Nucl. Fusion 57(14), 056018 (2017)
13. A. Kreter, Reactor-relevant plasma-material interaction studies in linear plasma devices. Fusion
Sci. Technol. 59, 51–56 (2011)
14. J.W. Coenen, G. Arnoux, B. Bazylev et al., ELM induced tungsten melting and its impact on
tokamak operation. J. Nucl. Mater. 463, 78–84 (2015)
15. G. Sergienko, B. Bazylev, T. Hirai, Experience with bulk tungsten test-limiters under high heat
loads: melting and melt layer propagation. Phys. Scr. T128, 81–86 (2007)
16. T. Tanabe, V. Philipps, B. Unterberg et al., High Z limiter test in TEXTOR. J. Nucl. Mater.
212–215, 1370–1378 (1994)
17. T. Tanabe, M. Fujine, H. Noguchi et al., High heat load test of molybdenum. J. Nucl. Mater.
200, 120–127 (1993)