34
2 Discharges in Current Large Tokamaks
systematic choice of the materials used in plasma machines gave important information on erosion/deposition, materials migration, hydrogen retention, and so on. One
good example is the observation of T profiles of PFS using tritium imaging plate in
TFTR, JT-60U, and JET. Figures 5.7 and 5.8 in Chap. 5 are examples of how T was
retained in deposited carbon layers on TFTR carbon tiles.
Collecting flakes and dust during the maintenance of plasma machines [22, 23]
and analyzing them are also important techniques to observe erosion deposition and
production of hazardous materials activated by neutron irradiation and contaminated
with T.
The following chapters on PMI of this book are based on results given by various
diagnostic methods described here.
References
1. Fusion Science and Technology, 47 Issue 2: Special Issue on TEXTOR (2005)
2. TFTR Public Home Page—Princeton Plasma Physics Laboratory https://w3.pppl.gov/tftr/
3. H. Mao, F. Ding, G. Luo et al., The impacts of lithium and silicon coating on the W source in
EAST, Nucl. Mater. Energy 12, 447–452 (2017)
4. JET: EUROfusion’s flagship device https://www.euro-fusion.org/devices/jet/
5. H. Takenaga and the JT-60 Team, Overview of JT-60U results for the development of a steadystate advanced tokamak scenario, Nuclear Fusion 47, S563 (2007)
6. K. Fujimoto, T. Nakano, H. Kubo, Spatial structure of volume recombination in JT-60U
detached Divertor plasmas, plasma–and fusion research 4, 025 (2009)
7. S. Brezinsek, P.T. Greenland, Ph Mertens, et al. Formation of HD Molecules in the Boundary
Layer of TEXTOR, Physica Scripta, T103 63–67 (2003)
8. T. Nakano, H. Kubo, N. Asakura, Volume recombination of C 4+ in detached divertor plasmas
of JT-60U, Nuclear. Fusion 47, 1458–1467 (2007)
9. T. Nakano, The JT-60 Team, Comparison of Ne and Ar seeded radiative divertor plasmas in
JT-60U, J. Nucl. Mater. 463, 555–560 (2015)
10. T. Nakano, N. Asakura, H. Kubo, Tungsten accumulation in H-mode plasmas of JT-60U,
Nuclear. Fusion 49, 115024 (2009)
11. T. Tanabe, M. Akiba, Y. Ueda, et al., On the utilization of high Z materials as plasma facing
component, Fusion Eng. and Design, 39–40, 275–285 (1998)
12. S. Sakurai, N. Asakura, N. Hosogane et al., Plasma characteristics near the X-point in W-shaped
divertor of JT-60U, J. Nucl. Mater. 266,1191–1196 (1999)
13. D.L.Rudakov, T. Abrams, R. Ding, et al., DiMES PMI research at DIII-D in support of ITER
and beyond, Fusion Eng. and Design 124, 196–201 (2017)
14. M. Rubel, S. Brezinsek, J.W. Coenen, et al., Overview of wall probes for erosion and deposition
studies in the TEXTOR tokamak, Matter and Radiation at Extremes 2, 87–104 (2017)
15. M. Mayer, V. Rohde, G. Ramos et al., Erosion of tungsten and carbon markers in the outer
divertor of ASDEX-Upgrade, Physica Scripta, T128, 106–110 (2007)
16. T. Tanabe, T. Ohgo, M. Wada, et al., Materials mixing on W/C twin limiter in TEXTOR-94,
Fusion Eng. and Design, 49–50, 355–362 (2000)
17. T. Hirai, V. Philipps, A. Huber, et al., Hydrogen recycling and microstructures of tantalum and
tungsten twin limiters exposed to TEXTOR-94, J. Nucl. Mater. 307–311, 79–83 (2002)
18. U. Samm, P. Bogen, G. Esser et al., Plasma edge physics with siliconization in TEXTOR, J.
Nucl. Mater., 220–222, 25–35 (1995)
19. J.P. Coad, H.-G. Esser, J. Likonen, et al., Diagnostics for studying deposition and erosion
processes in JET, Fusion Eng. Design, 74, 745–749 (2005)
2 Discharges in Current Large Tokamaks
systematic choice of the materials used in plasma machines gave important information on erosion/deposition, materials migration, hydrogen retention, and so on. One
good example is the observation of T profiles of PFS using tritium imaging plate in
TFTR, JT-60U, and JET. Figures 5.7 and 5.8 in Chap. 5 are examples of how T was
retained in deposited carbon layers on TFTR carbon tiles.
Collecting flakes and dust during the maintenance of plasma machines [22, 23]
and analyzing them are also important techniques to observe erosion deposition and
production of hazardous materials activated by neutron irradiation and contaminated
with T.
The following chapters on PMI of this book are based on results given by various
diagnostic methods described here.
References
1. Fusion Science and Technology, 47 Issue 2: Special Issue on TEXTOR (2005)
2. TFTR Public Home Page—Princeton Plasma Physics Laboratory https://w3.pppl.gov/tftr/
3. H. Mao, F. Ding, G. Luo et al., The impacts of lithium and silicon coating on the W source in
EAST, Nucl. Mater. Energy 12, 447–452 (2017)
4. JET: EUROfusion’s flagship device https://www.euro-fusion.org/devices/jet/
5. H. Takenaga and the JT-60 Team, Overview of JT-60U results for the development of a steadystate advanced tokamak scenario, Nuclear Fusion 47, S563 (2007)
6. K. Fujimoto, T. Nakano, H. Kubo, Spatial structure of volume recombination in JT-60U
detached Divertor plasmas, plasma–and fusion research 4, 025 (2009)
7. S. Brezinsek, P.T. Greenland, Ph Mertens, et al. Formation of HD Molecules in the Boundary
Layer of TEXTOR, Physica Scripta, T103 63–67 (2003)
8. T. Nakano, H. Kubo, N. Asakura, Volume recombination of C 4+ in detached divertor plasmas
of JT-60U, Nuclear. Fusion 47, 1458–1467 (2007)
9. T. Nakano, The JT-60 Team, Comparison of Ne and Ar seeded radiative divertor plasmas in
JT-60U, J. Nucl. Mater. 463, 555–560 (2015)
10. T. Nakano, N. Asakura, H. Kubo, Tungsten accumulation in H-mode plasmas of JT-60U,
Nuclear. Fusion 49, 115024 (2009)
11. T. Tanabe, M. Akiba, Y. Ueda, et al., On the utilization of high Z materials as plasma facing
component, Fusion Eng. and Design, 39–40, 275–285 (1998)
12. S. Sakurai, N. Asakura, N. Hosogane et al., Plasma characteristics near the X-point in W-shaped
divertor of JT-60U, J. Nucl. Mater. 266,1191–1196 (1999)
13. D.L.Rudakov, T. Abrams, R. Ding, et al., DiMES PMI research at DIII-D in support of ITER
and beyond, Fusion Eng. and Design 124, 196–201 (2017)
14. M. Rubel, S. Brezinsek, J.W. Coenen, et al., Overview of wall probes for erosion and deposition
studies in the TEXTOR tokamak, Matter and Radiation at Extremes 2, 87–104 (2017)
15. M. Mayer, V. Rohde, G. Ramos et al., Erosion of tungsten and carbon markers in the outer
divertor of ASDEX-Upgrade, Physica Scripta, T128, 106–110 (2007)
16. T. Tanabe, T. Ohgo, M. Wada, et al., Materials mixing on W/C twin limiter in TEXTOR-94,
Fusion Eng. and Design, 49–50, 355–362 (2000)
17. T. Hirai, V. Philipps, A. Huber, et al., Hydrogen recycling and microstructures of tantalum and
tungsten twin limiters exposed to TEXTOR-94, J. Nucl. Mater. 307–311, 79–83 (2002)
18. U. Samm, P. Bogen, G. Esser et al., Plasma edge physics with siliconization in TEXTOR, J.
Nucl. Mater., 220–222, 25–35 (1995)
19. J.P. Coad, H.-G. Esser, J. Likonen, et al., Diagnostics for studying deposition and erosion
processes in JET, Fusion Eng. Design, 74, 745–749 (2005)