130
7 Fundamentals of Hydrogen Recycling
18. T. Tanabe, Tritium handling issues in fusion reactor materials. J. Nucl. Mater. 417, 545–550
(2011)
19. S. Higashijima, The JT 60 Team, Wall conditioning to control Impurity and hydrogen isotope
recycling in JT-60U. J. Plasma Fusion Res. 75, 1297 (1999). (in Japanese)
20. M. Yoshida, T. Tanabe, A. Adachi et al., Carbon transport and fuel retention in JT-60U with
high temperature operation based on postmortem analysis. J. Nucl. Mater. 438, S1261–S1265
(2013)
21. D. Murdoch, M. Glugla, T. Hayashi et al., Evolution of ITER Tritium Confinement strategy
and adaptation to Cadarache site conditions and French regulatory requirements. Fusion Eng.
Design 83, 1355–1358 (2008)
22. J. Roth, E. Tsitrone, A. Loarte et al., Recent analysis of key plasma wall interactions issues for
ITER. J. Nucl. Mater. 390–391, 1 (2009)
23. E. Tsitrone, B. Pegourie, Y. Marande et al., Multi machine scaling of fuel retention in 4 carbon
dominated tokamaks. J. Nucl. Mater. 415, s735 (2011)
24. R.-D. Penzhorn, J.P. Coad, N. Bekris et al., Tritium in plasma facing components. Fusion Eng.
and Design 56–57, 105–116 (2001)
25. G.R. Longhurst, J. Ambrosek, Verification and validation of the tritium transport code TMAP7.
Fusion Sci. Technol. 48, 468–471 (2005)
26. S.T. Nakagawa, Y. Yamamura, Depth profiling and stoichiometric changes due to high-fluence
ion bombardments, Nucl. Instr. Methods, B33, 780–783 (1988)
27. T. Ono, T. Kenmotsu, T. Muramoto, T. Kawamura, Calculation of deuterium retention, reemission and reflection from a tungsten material under D + ions irradiation with ACATDIFFUSE code. J. Nucl. Mater. 390–391, 713–716 (2009)
7 Fundamentals of Hydrogen Recycling
18. T. Tanabe, Tritium handling issues in fusion reactor materials. J. Nucl. Mater. 417, 545–550
(2011)
19. S. Higashijima, The JT 60 Team, Wall conditioning to control Impurity and hydrogen isotope
recycling in JT-60U. J. Plasma Fusion Res. 75, 1297 (1999). (in Japanese)
20. M. Yoshida, T. Tanabe, A. Adachi et al., Carbon transport and fuel retention in JT-60U with
high temperature operation based on postmortem analysis. J. Nucl. Mater. 438, S1261–S1265
(2013)
21. D. Murdoch, M. Glugla, T. Hayashi et al., Evolution of ITER Tritium Confinement strategy
and adaptation to Cadarache site conditions and French regulatory requirements. Fusion Eng.
Design 83, 1355–1358 (2008)
22. J. Roth, E. Tsitrone, A. Loarte et al., Recent analysis of key plasma wall interactions issues for
ITER. J. Nucl. Mater. 390–391, 1 (2009)
23. E. Tsitrone, B. Pegourie, Y. Marande et al., Multi machine scaling of fuel retention in 4 carbon
dominated tokamaks. J. Nucl. Mater. 415, s735 (2011)
24. R.-D. Penzhorn, J.P. Coad, N. Bekris et al., Tritium in plasma facing components. Fusion Eng.
and Design 56–57, 105–116 (2001)
25. G.R. Longhurst, J. Ambrosek, Verification and validation of the tritium transport code TMAP7.
Fusion Sci. Technol. 48, 468–471 (2005)
26. S.T. Nakagawa, Y. Yamamura, Depth profiling and stoichiometric changes due to high-fluence
ion bombardments, Nucl. Instr. Methods, B33, 780–783 (1988)
27. T. Ono, T. Kenmotsu, T. Muramoto, T. Kawamura, Calculation of deuterium retention, reemission and reflection from a tungsten material under D + ions irradiation with ACATDIFFUSE code. J. Nucl. Mater. 390–391, 713–716 (2009)