References
93
References
1. Y. Gotoh, T. Tanabe, Y. Ishimoto et al., Long-term erosion and re-deposition of carbon in the
divertor region of JT-60U. J. Nucl. Mater. 357, 138–146 (2006)
2. J.N. Brooks, J.P. Allain, D. Whyte et al., Analysis of C-MOD molybdenum divertor erosion
and code/data comparison. J. Nucl. Mater. 415, S112–S116 (2011)
3. Y. Ishimoto, Y. Gotoh, T. Arai et al., Transport studies of carbon impurities using 13 CH 4 gas
puffing in JT-60U, Proceedings of 12th International Conference on Fusion Reactor Materials,
Santa Barbara, USA 4–10 Dec 2005 (2005)
4. Y. Ueda, M. Fukumoto, J. Watanabe et al., Localized tungsten deposition in divertor region in
JT-60U. Nucl. Fusion 49, 065027 (2009)
5. Y. Gotoh, T. Arai, J. Yagyu et al., Transmission electron microscopy of redeposition layers on
graphite tiles used for open divertor armor of JT-60. J. Nucl. Mater. 329–333, 840–844 (2004)
6. K. Sugiyama, K. Miyasaka, T. Tanabe et al., Tritium distribution on the surface of plasma
facing carbon tiles used in JET. J. Nucl. Mater. 313–316, 507–513 (2003)
7. J.P. Coad, N. Bekris, J.D. Elder et al., Erosion/deposition issues at JET. J. Nucl. Mater. 290–293,
224–230 (2001)
8. T. Tanabe, K. Sugiyama, C.H. Skinner, N. Bekris, C.A. Gentile, J.P. Coad, Tritium Retention
in the Gap between the Plasma-Facing Carbon Tiles Used in D-T Discharge Phase in JET and
TFTR. Fusion Science and Technology 48, 577–580 (2017)
9. R. Behrisch, M. Mayer, C. Garcia-Rosales, Composition of the plasma facing material
Tokamakium. J. Nucl. Mater. 233–237, 673–680 (1996)
10. N. Bekris, J.P. Coad, R.-D. Penzhorn et al., Characterization of flakes generated in JET after
DD and DT plasma operations. J. Nucl. Mater. 337–339, 659–663 (2005)
11. A.T. Peacock, P. Andrew, P. Cetier et al., Dust and fakes in the JET MkIIa divertor, analysis
and results. J. Nucl. Mater. 266–269, 423–428 (1999)
12. A. Baron-Wiechec, E. Fortuna-Zale´ sna, J. Grzonka, First dust study in JET with the ITER-like
wall: sampling, analysis and classification. Nucl. Fusion 55(7), 113033 (2015)
13. J.P. Sharpe, D.A. Petti, H.-W. Bartels, A review of dust in fusion devices: Implications for
safety and operational performance. Fusion Eng. Des. 63–64, 153–163 (2002)
14. K. Sugiyama, T. Tanabe, K. Masaki et al., Tritium distribution measurement of the tile gap of
JT-60U. J. Nucl. Mater. 367–370, 1248–1253 (2007)
15. T. Tanabe, K. Sugiyama, C.H. Skinner, N. Bekris, C.A. Gentile, J.P. Coad, Tritium Retention
in the Gap between the Plasma-Facing Carbon Tiles Used in D-T Discharge Phase in JET and
TFTR. Fusion Science and Technology 48(1), 577–580 (2017)
93
References
1. Y. Gotoh, T. Tanabe, Y. Ishimoto et al., Long-term erosion and re-deposition of carbon in the
divertor region of JT-60U. J. Nucl. Mater. 357, 138–146 (2006)
2. J.N. Brooks, J.P. Allain, D. Whyte et al., Analysis of C-MOD molybdenum divertor erosion
and code/data comparison. J. Nucl. Mater. 415, S112–S116 (2011)
3. Y. Ishimoto, Y. Gotoh, T. Arai et al., Transport studies of carbon impurities using 13 CH 4 gas
puffing in JT-60U, Proceedings of 12th International Conference on Fusion Reactor Materials,
Santa Barbara, USA 4–10 Dec 2005 (2005)
4. Y. Ueda, M. Fukumoto, J. Watanabe et al., Localized tungsten deposition in divertor region in
JT-60U. Nucl. Fusion 49, 065027 (2009)
5. Y. Gotoh, T. Arai, J. Yagyu et al., Transmission electron microscopy of redeposition layers on
graphite tiles used for open divertor armor of JT-60. J. Nucl. Mater. 329–333, 840–844 (2004)
6. K. Sugiyama, K. Miyasaka, T. Tanabe et al., Tritium distribution on the surface of plasma
facing carbon tiles used in JET. J. Nucl. Mater. 313–316, 507–513 (2003)
7. J.P. Coad, N. Bekris, J.D. Elder et al., Erosion/deposition issues at JET. J. Nucl. Mater. 290–293,
224–230 (2001)
8. T. Tanabe, K. Sugiyama, C.H. Skinner, N. Bekris, C.A. Gentile, J.P. Coad, Tritium Retention
in the Gap between the Plasma-Facing Carbon Tiles Used in D-T Discharge Phase in JET and
TFTR. Fusion Science and Technology 48, 577–580 (2017)
9. R. Behrisch, M. Mayer, C. Garcia-Rosales, Composition of the plasma facing material
Tokamakium. J. Nucl. Mater. 233–237, 673–680 (1996)
10. N. Bekris, J.P. Coad, R.-D. Penzhorn et al., Characterization of flakes generated in JET after
DD and DT plasma operations. J. Nucl. Mater. 337–339, 659–663 (2005)
11. A.T. Peacock, P. Andrew, P. Cetier et al., Dust and fakes in the JET MkIIa divertor, analysis
and results. J. Nucl. Mater. 266–269, 423–428 (1999)
12. A. Baron-Wiechec, E. Fortuna-Zale´ sna, J. Grzonka, First dust study in JET with the ITER-like
wall: sampling, analysis and classification. Nucl. Fusion 55(7), 113033 (2015)
13. J.P. Sharpe, D.A. Petti, H.-W. Bartels, A review of dust in fusion devices: Implications for
safety and operational performance. Fusion Eng. Des. 63–64, 153–163 (2002)
14. K. Sugiyama, T. Tanabe, K. Masaki et al., Tritium distribution measurement of the tile gap of
JT-60U. J. Nucl. Mater. 367–370, 1248–1253 (2007)
15. T. Tanabe, K. Sugiyama, C.H. Skinner, N. Bekris, C.A. Gentile, J.P. Coad, Tritium Retention
in the Gap between the Plasma-Facing Carbon Tiles Used in D-T Discharge Phase in JET and
TFTR. Fusion Science and Technology 48(1), 577–580 (2017)
