Plasma-facing material (English Wikipedia)

Analysis of information sources in references of the Wikipedia article "Plasma-facing material" in English language version.

refsWebsite

Global rank English rank

24doi.org

2^nd place

19harvard.edu

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7semanticscholar.org

11^th place

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5web.archive.org

1^st place

3handle.net

102^nd place

76^th place

3sciencedirect.com

149^th place

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2osti.gov

2,036^th place

1,254^th place

2mpg.de

1,624^th place

1,592^nd place

2worldcat.org

5^th place

2researchgate.net

120^th place

125^th place

2arxiv.org

69^th place

59^th place

1columbia.edu

488^th place

374^th place

1phys.org

1,283^rd place

1,130^th place

1pppl.gov

low place

1zenodo.org

621^st place

380^th place

1science.org

1,160^th place

737^th place

1hal.science

low place

1mit.edu

415^th place

327^th place

1nih.gov

4^th place

arxiv.org

Abrams, T.; et al. (2021). "Evaluation of silicon carbide as a divertor armor material in DIII-D H-mode discharges". Nuclear Fusion. 61 (6): 066005. arXiv:2104.04083. Bibcode:2021NucFu..61f6005A. doi:10.1088/1741-4326/abecee. S2CID 233204645.
Effenberg, F.; Abe, S.; Sinclair, G.; et al. (2023). "In-situ coating of silicon-rich films on tokamak plasma-facing components with real-time Si material injection". Nuclear Fusion. 63 (10): 106004. arXiv:2304.03923. Bibcode:2023NucFu..63j6004E. doi:10.1088/1741-4326/acee98. S2CID 258049235.

columbia.edu

apam.columbia.edu

Stoafer, Chris (14 April 2011). "Tokamak Divertor System Concept and the Design for ITER" (PDF). Applied Physics and Applied Math at Columbia University. Archived from the original (PDF) on 11 December 2013. Retrieved 20 April 2019.

doi.org

Ono, Masayuki (2012). Lithium as Plasma Facing Component for Magnetic Fusion Research (Report). Princeton Plasma Physics Lab. doi:10.2172/1056493. OSTI 1056493.
Ihli, T; Basu, T.K; Giancarli, L.M; Konishi, S; Malang, S; Najmabadi, F; Nishio, S; Raffray, A.R.; Rao, C.V.S; Sagara, A; Wu, Y (December 2008). "Review of blanket designs for advanced fusion reactors". Fusion Engineering and Design. 83 (7–9): 912–919. Bibcode:2008FusED..83..912I. doi:10.1016/j.fusengdes.2008.07.039.
Ando, T.; Kodama, K.; Matsukawa, M.; Ouchi, Y.; Arai, T.; Yagyu, J.; Kaminaga, A.; Sasajima, T.; Koike, T.; Shimizu, M. (1994). "Material behavior of JT-60U plasma facing components and installation of B/Sub 4/C-converted CFC/Graphite tiles". 15th IEEE/NPSS Symposium. Fusion Engineering. Vol. 1. pp. 541–544. doi:10.1109/FUSION.1993.518390. ISBN 0-7803-1412-3.
Hino, T; Jinushi, T; Yamauchi, Y; Hashiba, M.; Hirohata, Y.; Katoh, Y.; Kohyama, A. (2012). "Silicon Carbide as Plasma Facing or Blanket Material". Advanced SiC/SiC Ceramic Composites: Developments and Applications in Energy Systems. Ceramic Transactions Series. Vol. 144. pp. 353–361. doi:10.1002/9781118406014.ch32. ISBN 9781118406014.
Kaita R, Berzak L, Boyle D (29 April 2010). "Experiments with liquid metal walls: Status of the lithium tokamak experiment". Fusion Engineering and Design. 85 (6): 874–881. Bibcode:2010FusED..85..874K. doi:10.1016/j.fusengdes.2010.04.005. OSTI 973198. S2CID 120010130.
Ono, M.; et al. (2013). "Recent progress in the NSTX/NSTX-U lithium programme and prospects for reactor-relevant liquid-lithium based divertor development". Nuclear Fusion. 53 (11). Bibcode:2013NucFu..53k3030O. doi:10.1088/0029-5515/53/11/113030.
Goranson, P.; Barnes, G.; Chrzanowski, J.; Heitzenroeder, P.; Nelson, B.; Neumeyer, C.; Ping, J. (1999). Design of the plasma facing components for the National Spherical Tokamak Experiment (NSTX). 18th IEEE/NPSS Symposium on Fusion Engineering. doi:10.1109/FUSION.1999.849793.
Diez, M.; Balden, M.; Brezinsek, S.; Corre, Y.; Fedorczak, N.; Firdaouss, M.; Fortuna, E.; Gaspar, J.; Gunn, J. P.; Hakola, A.; Loarer, T.; Martin, C.; Mayer, M.; Reilhac, P.; Richou, M. (2023-03-01). "Overview of plasma-tungsten surfaces interactions on the divertor test sector in WEST during the C3 and C4 campaigns". Nuclear Materials and Energy. 34: 101399. Bibcode:2023NMEne..3401399D. doi:10.1016/j.nme.2023.101399. ISSN 2352-1791.
Neu, R.; et al. (December 1996). "The tungsten divertor experiment at ASDEX Upgrade". Plasma Physics and Controlled Fusion. 38 (12A): A165 – A179. doi:10.1088/0741-3335/38/12A/013. S2CID 250893393.
Petty, C.C.; DIII-D Team (5 June 2019). "DIII-D research twoards establishing the scientific basis for future fusion reactors" (PDF). Nuclear Fusion. 59 (11): 112002. Bibcode:2019NucFu..59k2002P. doi:10.1088/1741-4326/ab024a. S2CID 127950712.
Evans, Ll. M.; Margetts, L.; Casalegno, V.; Lever, L. M.; Bushell, J.; Lowe, T.; Wallwork, A.; Young, P.; Lindemann, A. (2015-05-28). "Transient thermal finite element analysis of CFC–Cu ITER monoblock using X-ray tomography data". Fusion Engineering and Design. 100: 100–111. Bibcode:2015FusED.100..100E. doi:10.1016/j.fusengdes.2015.04.048. hdl:10871/17772.
Evans, Ll. M.; Margetts, L.; Casalegno, V.; Leonard, F.; Lowe, T.; Lee, P. D.; Schmidt, M.; Mummery, P. M. (2014-06-01). "Thermal characterisation of ceramic/metal joining techniques for fusion applications using X-ray tomography". Fusion Engineering and Design. 89 (6): 826–836. Bibcode:2014FusED..89..826E. doi:10.1016/j.fusengdes.2014.05.002.
Neu, R.; et al. (2005). "Tungsten: an option for divertor and main chamber plasma facing components in future fusion devices". Nuclear Fusion. 45 (3): 209–218. Bibcode:2005NucFu..45..209N. doi:10.1088/0029-5515/45/3/007. S2CID 56572005.
Philipps, V.; et al. (2011). "Tungsten as material for plasma-facing components in fusion devices". Journal of Nuclear Materials. 415 (1): S2 – S9. Bibcode:2011JNuM..415S...2P. doi:10.1016/j.jnucmat.2011.01.110.
Neu, R.; et al. (2016). "Advanced tungsten materials for plasma-facing components of DEMO and fusion power plants". Fusion Engineering and Design. 109–111: 1046–1052. Bibcode:2016FusED.109.1046N. doi:10.1016/j.fusengdes.2016.01.027. hdl:11858/00-001M-0000-002B-3142-7.
Abrams, T.; et al. (2021). "Evaluation of silicon carbide as a divertor armor material in DIII-D H-mode discharges". Nuclear Fusion. 61 (6): 066005. arXiv:2104.04083. Bibcode:2021NucFu..61f6005A. doi:10.1088/1741-4326/abecee. S2CID 233204645.
Mayer, M.; Balden, M.; Behrisch, R. (1998). "Deuterium retention in carbides and doped graphites". Journal of Nuclear Materials. 252 (1): 55–62. Bibcode:1998JNuM..252...55M. doi:10.1016/S0022-3115(97)00299-7.
Koller, Markus T.; Davis, James W.; Goodland, Megan E.; Abrams, Tyler; Gonderman, Sean; Herdrich, Georg; Frieß, Martin; Zuber, Christian (2019). "Deuterium retention in silicon carbide, SiC ceramic matrix composites, and SiC coated graphite". Nuclear Materials and Energy. 20: 100704. Bibcode:2019NMEne..2000704K. doi:10.1016/j.nme.2019.100704.
Roth, Joachim; Tsitrone, E.; Loarte, A.; Loarer, Th.; Counsell, G.; Neu, R.; Philipps, V.; Brezinsek, S.; Lehnen, M.; Coad, P.; Grisolia, Ch.; Schmid, K.; Krieger, K.; Kallenbach, A.; Lipschultz, B.; Doerner, R.; Causey, R.; Alimov, V.; Shu, W.; Ogorodnikova, O.; Kirschner, A.; Federici, G.; Kukushkin, A. (2009). "Recent analysis of key plasma wall interactions issues for ITER". Journal of Nuclear Materials. 390–391: 1–9. Bibcode:2009JNuM..390....1R. doi:10.1016/j.jnucmat.2009.01.037. hdl:11858/00-001M-0000-0026-F442-2. ISSN 0022-3115.
Katoh, Y.; et al. (2012). "Radiation effects in SiC for nuclear structural applications". Current Opinion in Solid State and Materials Science. 16 (3): 143–152. Bibcode:2012COSSM..16..143K. doi:10.1016/j.cossms.2012.03.005.
Koyanagi, T.; et al. (2018). "Recent progress in the development of SiC composites for nuclear fusion applications". Journal of Nuclear Materials. 511: 544–555. Bibcode:2018JNuM..511..544K. doi:10.1016/j.jnucmat.2018.06.017. S2CID 104235507.
Winter, J.; et al. (1993). "Improved plasma performance in TEXTOR with silicon coated surfaces". Phys. Rev. Lett. 71 (10): 1549–1552. Bibcode:1993PhRvL..71.1549W. doi:10.1103/PhysRevLett.71.1549. PMID 10054436.
Samm, U.; et al. (1995). "Plasma edge physics with siliconization in TEXTOR". Journal of Nuclear Materials. 220–222: 25–35. Bibcode:1995JNuM..220...25S. doi:10.1016/0022-3115(94)00444-7.
Effenberg, F.; Abe, S.; Sinclair, G.; et al. (2023). "In-situ coating of silicon-rich films on tokamak plasma-facing components with real-time Si material injection". Nuclear Fusion. 63 (10): 106004. arXiv:2304.03923. Bibcode:2023NucFu..63j6004E. doi:10.1088/1741-4326/acee98. S2CID 258049235.

hal.science

amu.hal.science

Diez, M.; Balden, M.; Brezinsek, S.; Corre, Y.; Fedorczak, N.; Firdaouss, M.; Fortuna, E.; Gaspar, J.; Gunn, J. P.; Hakola, A.; Loarer, T.; Martin, C.; Mayer, M.; Reilhac, P.; Richou, M. (2023-03-01). "Overview of plasma-tungsten surfaces interactions on the divertor test sector in WEST during the C3 and C4 campaigns". Nuclear Materials and Energy. 34: 101399. Bibcode:2023NMEne..3401399D. doi:10.1016/j.nme.2023.101399. ISSN 2352-1791.

handle.net

hdl.handle.net

Evans, Ll. M.; Margetts, L.; Casalegno, V.; Lever, L. M.; Bushell, J.; Lowe, T.; Wallwork, A.; Young, P.; Lindemann, A. (2015-05-28). "Transient thermal finite element analysis of CFC–Cu ITER monoblock using X-ray tomography data". Fusion Engineering and Design. 100: 100–111. Bibcode:2015FusED.100..100E. doi:10.1016/j.fusengdes.2015.04.048. hdl:10871/17772.
Neu, R.; et al. (2016). "Advanced tungsten materials for plasma-facing components of DEMO and fusion power plants". Fusion Engineering and Design. 109–111: 1046–1052. Bibcode:2016FusED.109.1046N. doi:10.1016/j.fusengdes.2016.01.027. hdl:11858/00-001M-0000-002B-3142-7.
Roth, Joachim; Tsitrone, E.; Loarte, A.; Loarer, Th.; Counsell, G.; Neu, R.; Philipps, V.; Brezinsek, S.; Lehnen, M.; Coad, P.; Grisolia, Ch.; Schmid, K.; Krieger, K.; Kallenbach, A.; Lipschultz, B.; Doerner, R.; Causey, R.; Alimov, V.; Shu, W.; Ogorodnikova, O.; Kirschner, A.; Federici, G.; Kukushkin, A. (2009). "Recent analysis of key plasma wall interactions issues for ITER". Journal of Nuclear Materials. 390–391: 1–9. Bibcode:2009JNuM..390....1R. doi:10.1016/j.jnucmat.2009.01.037. hdl:11858/00-001M-0000-0026-F442-2. ISSN 0022-3115.

harvard.edu

ui.adsabs.harvard.edu

Ihli, T; Basu, T.K; Giancarli, L.M; Konishi, S; Malang, S; Najmabadi, F; Nishio, S; Raffray, A.R.; Rao, C.V.S; Sagara, A; Wu, Y (December 2008). "Review of blanket designs for advanced fusion reactors". Fusion Engineering and Design. 83 (7–9): 912–919. Bibcode:2008FusED..83..912I. doi:10.1016/j.fusengdes.2008.07.039.
Kaita R, Berzak L, Boyle D (29 April 2010). "Experiments with liquid metal walls: Status of the lithium tokamak experiment". Fusion Engineering and Design. 85 (6): 874–881. Bibcode:2010FusED..85..874K. doi:10.1016/j.fusengdes.2010.04.005. OSTI 973198. S2CID 120010130.
Ono, M.; et al. (2013). "Recent progress in the NSTX/NSTX-U lithium programme and prospects for reactor-relevant liquid-lithium based divertor development". Nuclear Fusion. 53 (11). Bibcode:2013NucFu..53k3030O. doi:10.1088/0029-5515/53/11/113030.
Diez, M.; Balden, M.; Brezinsek, S.; Corre, Y.; Fedorczak, N.; Firdaouss, M.; Fortuna, E.; Gaspar, J.; Gunn, J. P.; Hakola, A.; Loarer, T.; Martin, C.; Mayer, M.; Reilhac, P.; Richou, M. (2023-03-01). "Overview of plasma-tungsten surfaces interactions on the divertor test sector in WEST during the C3 and C4 campaigns". Nuclear Materials and Energy. 34: 101399. Bibcode:2023NMEne..3401399D. doi:10.1016/j.nme.2023.101399. ISSN 2352-1791.
Petty, C.C.; DIII-D Team (5 June 2019). "DIII-D research twoards establishing the scientific basis for future fusion reactors" (PDF). Nuclear Fusion. 59 (11): 112002. Bibcode:2019NucFu..59k2002P. doi:10.1088/1741-4326/ab024a. S2CID 127950712.
Evans, Ll. M.; Margetts, L.; Casalegno, V.; Lever, L. M.; Bushell, J.; Lowe, T.; Wallwork, A.; Young, P.; Lindemann, A. (2015-05-28). "Transient thermal finite element analysis of CFC–Cu ITER monoblock using X-ray tomography data". Fusion Engineering and Design. 100: 100–111. Bibcode:2015FusED.100..100E. doi:10.1016/j.fusengdes.2015.04.048. hdl:10871/17772.
Evans, Ll. M.; Margetts, L.; Casalegno, V.; Leonard, F.; Lowe, T.; Lee, P. D.; Schmidt, M.; Mummery, P. M. (2014-06-01). "Thermal characterisation of ceramic/metal joining techniques for fusion applications using X-ray tomography". Fusion Engineering and Design. 89 (6): 826–836. Bibcode:2014FusED..89..826E. doi:10.1016/j.fusengdes.2014.05.002.
Neu, R.; et al. (2005). "Tungsten: an option for divertor and main chamber plasma facing components in future fusion devices". Nuclear Fusion. 45 (3): 209–218. Bibcode:2005NucFu..45..209N. doi:10.1088/0029-5515/45/3/007. S2CID 56572005.
Philipps, V.; et al. (2011). "Tungsten as material for plasma-facing components in fusion devices". Journal of Nuclear Materials. 415 (1): S2 – S9. Bibcode:2011JNuM..415S...2P. doi:10.1016/j.jnucmat.2011.01.110.
Neu, R.; et al. (2016). "Advanced tungsten materials for plasma-facing components of DEMO and fusion power plants". Fusion Engineering and Design. 109–111: 1046–1052. Bibcode:2016FusED.109.1046N. doi:10.1016/j.fusengdes.2016.01.027. hdl:11858/00-001M-0000-002B-3142-7.
Abrams, T.; et al. (2021). "Evaluation of silicon carbide as a divertor armor material in DIII-D H-mode discharges". Nuclear Fusion. 61 (6): 066005. arXiv:2104.04083. Bibcode:2021NucFu..61f6005A. doi:10.1088/1741-4326/abecee. S2CID 233204645.
Mayer, M.; Balden, M.; Behrisch, R. (1998). "Deuterium retention in carbides and doped graphites". Journal of Nuclear Materials. 252 (1): 55–62. Bibcode:1998JNuM..252...55M. doi:10.1016/S0022-3115(97)00299-7.
Koller, Markus T.; Davis, James W.; Goodland, Megan E.; Abrams, Tyler; Gonderman, Sean; Herdrich, Georg; Frieß, Martin; Zuber, Christian (2019). "Deuterium retention in silicon carbide, SiC ceramic matrix composites, and SiC coated graphite". Nuclear Materials and Energy. 20: 100704. Bibcode:2019NMEne..2000704K. doi:10.1016/j.nme.2019.100704.
Roth, Joachim; Tsitrone, E.; Loarte, A.; Loarer, Th.; Counsell, G.; Neu, R.; Philipps, V.; Brezinsek, S.; Lehnen, M.; Coad, P.; Grisolia, Ch.; Schmid, K.; Krieger, K.; Kallenbach, A.; Lipschultz, B.; Doerner, R.; Causey, R.; Alimov, V.; Shu, W.; Ogorodnikova, O.; Kirschner, A.; Federici, G.; Kukushkin, A. (2009). "Recent analysis of key plasma wall interactions issues for ITER". Journal of Nuclear Materials. 390–391: 1–9. Bibcode:2009JNuM..390....1R. doi:10.1016/j.jnucmat.2009.01.037. hdl:11858/00-001M-0000-0026-F442-2. ISSN 0022-3115.
Katoh, Y.; et al. (2012). "Radiation effects in SiC for nuclear structural applications". Current Opinion in Solid State and Materials Science. 16 (3): 143–152. Bibcode:2012COSSM..16..143K. doi:10.1016/j.cossms.2012.03.005.
Koyanagi, T.; et al. (2018). "Recent progress in the development of SiC composites for nuclear fusion applications". Journal of Nuclear Materials. 511: 544–555. Bibcode:2018JNuM..511..544K. doi:10.1016/j.jnucmat.2018.06.017. S2CID 104235507.
Winter, J.; et al. (1993). "Improved plasma performance in TEXTOR with silicon coated surfaces". Phys. Rev. Lett. 71 (10): 1549–1552. Bibcode:1993PhRvL..71.1549W. doi:10.1103/PhysRevLett.71.1549. PMID 10054436.
Samm, U.; et al. (1995). "Plasma edge physics with siliconization in TEXTOR". Journal of Nuclear Materials. 220–222: 25–35. Bibcode:1995JNuM..220...25S. doi:10.1016/0022-3115(94)00444-7.
Effenberg, F.; Abe, S.; Sinclair, G.; et al. (2023). "In-situ coating of silicon-rich films on tokamak plasma-facing components with real-time Si material injection". Nuclear Fusion. 63 (10): 106004. arXiv:2304.03923. Bibcode:2023NucFu..63j6004E. doi:10.1088/1741-4326/acee98. S2CID 258049235.

mit.edu

dspace.mit.edu

Petty, C.C.; DIII-D Team (5 June 2019). "DIII-D research twoards establishing the scientific basis for future fusion reactors" (PDF). Nuclear Fusion. 59 (11): 112002. Bibcode:2019NucFu..59k2002P. doi:10.1088/1741-4326/ab024a. S2CID 127950712.

mpg.de

ipp.mpg.de

"Development of Boron Carbide Coated First Wall Components for Wendelstein 7-X". Max Planck Gesellschaft. Archived from the original on 12 May 2011.
"Examples of Test Coatings for the ASDEX Upgrade Tungsten First Wall: Comparison of Different Coating Method". Max Planck Gesellschaft. Archived from the original on 13 May 2011.

nih.gov

pubmed.ncbi.nlm.nih.gov

Winter, J.; et al. (1993). "Improved plasma performance in TEXTOR with silicon coated surfaces". Phys. Rev. Lett. 71 (10): 1549–1552. Bibcode:1993PhRvL..71.1549W. doi:10.1103/PhysRevLett.71.1549. PMID 10054436.

osti.gov

Ono, Masayuki (2012). Lithium as Plasma Facing Component for Magnetic Fusion Research (Report). Princeton Plasma Physics Lab. doi:10.2172/1056493. OSTI 1056493.
Kaita R, Berzak L, Boyle D (29 April 2010). "Experiments with liquid metal walls: Status of the lithium tokamak experiment". Fusion Engineering and Design. 85 (6): 874–881. Bibcode:2010FusED..85..874K. doi:10.1016/j.fusengdes.2010.04.005. OSTI 973198. S2CID 120010130.

phys.org

"Mitigating corrosion by liquid tin could lead to better cooling in fusion reactors". phys.org. Dec 2022. Archived from the original on 28 December 2022. Retrieved 22 July 2024.

pppl.gov

"The Lithium Tokamak Experiment (LTX)" (PDF). Fact Sheet. Princeton Plasma Physics Laboratory. March 2011. Archived from the original (PDF) on 4 March 2016. Retrieved 20 April 2019.

researchgate.net

Evans, Ll. M.; Margetts, L.; Casalegno, V.; Lever, L. M.; Bushell, J.; Lowe, T.; Wallwork, A.; Young, P.; Lindemann, A. (2015-05-28). "Transient thermal finite element analysis of CFC–Cu ITER monoblock using X-ray tomography data". Fusion Engineering and Design. 100: 100–111. Bibcode:2015FusED.100..100E. doi:10.1016/j.fusengdes.2015.04.048. hdl:10871/17772.
Evans, Ll. M.; Margetts, L.; Casalegno, V.; Leonard, F.; Lowe, T.; Lee, P. D.; Schmidt, M.; Mummery, P. M. (2014-06-01). "Thermal characterisation of ceramic/metal joining techniques for fusion applications using X-ray tomography". Fusion Engineering and Design. 89 (6): 826–836. Bibcode:2014FusED..89..826E. doi:10.1016/j.fusengdes.2014.05.002.

science.org

Heirbaut, Jim (16 August 2012). "How to Line a Thermonuclear Reactor". Science. Retrieved 20 April 2019.

sciencedirect.com

Mayer, M.; Balden, M.; Behrisch, R. (1998). "Deuterium retention in carbides and doped graphites". Journal of Nuclear Materials. 252 (1): 55–62. Bibcode:1998JNuM..252...55M. doi:10.1016/S0022-3115(97)00299-7.
Koller, Markus T.; Davis, James W.; Goodland, Megan E.; Abrams, Tyler; Gonderman, Sean; Herdrich, Georg; Frieß, Martin; Zuber, Christian (2019). "Deuterium retention in silicon carbide, SiC ceramic matrix composites, and SiC coated graphite". Nuclear Materials and Energy. 20: 100704. Bibcode:2019NMEne..2000704K. doi:10.1016/j.nme.2019.100704.
Roth, Joachim; Tsitrone, E.; Loarte, A.; Loarer, Th.; Counsell, G.; Neu, R.; Philipps, V.; Brezinsek, S.; Lehnen, M.; Coad, P.; Grisolia, Ch.; Schmid, K.; Krieger, K.; Kallenbach, A.; Lipschultz, B.; Doerner, R.; Causey, R.; Alimov, V.; Shu, W.; Ogorodnikova, O.; Kirschner, A.; Federici, G.; Kukushkin, A. (2009). "Recent analysis of key plasma wall interactions issues for ITER". Journal of Nuclear Materials. 390–391: 1–9. Bibcode:2009JNuM..390....1R. doi:10.1016/j.jnucmat.2009.01.037. hdl:11858/00-001M-0000-0026-F442-2. ISSN 0022-3115.

semanticscholar.org

api.semanticscholar.org

Kaita R, Berzak L, Boyle D (29 April 2010). "Experiments with liquid metal walls: Status of the lithium tokamak experiment". Fusion Engineering and Design. 85 (6): 874–881. Bibcode:2010FusED..85..874K. doi:10.1016/j.fusengdes.2010.04.005. OSTI 973198. S2CID 120010130.
Neu, R.; et al. (December 1996). "The tungsten divertor experiment at ASDEX Upgrade". Plasma Physics and Controlled Fusion. 38 (12A): A165 – A179. doi:10.1088/0741-3335/38/12A/013. S2CID 250893393.
Petty, C.C.; DIII-D Team (5 June 2019). "DIII-D research twoards establishing the scientific basis for future fusion reactors" (PDF). Nuclear Fusion. 59 (11): 112002. Bibcode:2019NucFu..59k2002P. doi:10.1088/1741-4326/ab024a. S2CID 127950712.
Neu, R.; et al. (2005). "Tungsten: an option for divertor and main chamber plasma facing components in future fusion devices". Nuclear Fusion. 45 (3): 209–218. Bibcode:2005NucFu..45..209N. doi:10.1088/0029-5515/45/3/007. S2CID 56572005.
Abrams, T.; et al. (2021). "Evaluation of silicon carbide as a divertor armor material in DIII-D H-mode discharges". Nuclear Fusion. 61 (6): 066005. arXiv:2104.04083. Bibcode:2021NucFu..61f6005A. doi:10.1088/1741-4326/abecee. S2CID 233204645.
Koyanagi, T.; et al. (2018). "Recent progress in the development of SiC composites for nuclear fusion applications". Journal of Nuclear Materials. 511: 544–555. Bibcode:2018JNuM..511..544K. doi:10.1016/j.jnucmat.2018.06.017. S2CID 104235507.
Effenberg, F.; Abe, S.; Sinclair, G.; et al. (2023). "In-situ coating of silicon-rich films on tokamak plasma-facing components with real-time Si material injection". Nuclear Fusion. 63 (10): 106004. arXiv:2304.03923. Bibcode:2023NucFu..63j6004E. doi:10.1088/1741-4326/acee98. S2CID 258049235.

web.archive.org

Stoafer, Chris (14 April 2011). "Tokamak Divertor System Concept and the Design for ITER" (PDF). Applied Physics and Applied Math at Columbia University. Archived from the original (PDF) on 11 December 2013. Retrieved 20 April 2019.
"Mitigating corrosion by liquid tin could lead to better cooling in fusion reactors". phys.org. Dec 2022. Archived from the original on 28 December 2022. Retrieved 22 July 2024.
"Development of Boron Carbide Coated First Wall Components for Wendelstein 7-X". Max Planck Gesellschaft. Archived from the original on 12 May 2011.
"The Lithium Tokamak Experiment (LTX)" (PDF). Fact Sheet. Princeton Plasma Physics Laboratory. March 2011. Archived from the original (PDF) on 4 March 2016. Retrieved 20 April 2019.
"Examples of Test Coatings for the ASDEX Upgrade Tungsten First Wall: Comparison of Different Coating Method". Max Planck Gesellschaft. Archived from the original on 13 May 2011.

worldcat.org

search.worldcat.org

Diez, M.; Balden, M.; Brezinsek, S.; Corre, Y.; Fedorczak, N.; Firdaouss, M.; Fortuna, E.; Gaspar, J.; Gunn, J. P.; Hakola, A.; Loarer, T.; Martin, C.; Mayer, M.; Reilhac, P.; Richou, M. (2023-03-01). "Overview of plasma-tungsten surfaces interactions on the divertor test sector in WEST during the C3 and C4 campaigns". Nuclear Materials and Energy. 34: 101399. Bibcode:2023NMEne..3401399D. doi:10.1016/j.nme.2023.101399. ISSN 2352-1791.
Roth, Joachim; Tsitrone, E.; Loarte, A.; Loarer, Th.; Counsell, G.; Neu, R.; Philipps, V.; Brezinsek, S.; Lehnen, M.; Coad, P.; Grisolia, Ch.; Schmid, K.; Krieger, K.; Kallenbach, A.; Lipschultz, B.; Doerner, R.; Causey, R.; Alimov, V.; Shu, W.; Ogorodnikova, O.; Kirschner, A.; Federici, G.; Kukushkin, A. (2009). "Recent analysis of key plasma wall interactions issues for ITER". Journal of Nuclear Materials. 390–391: 1–9. Bibcode:2009JNuM..390....1R. doi:10.1016/j.jnucmat.2009.01.037. hdl:11858/00-001M-0000-0026-F442-2. ISSN 0022-3115.

zenodo.org

Kaita R, Berzak L, Boyle D (29 April 2010). "Experiments with liquid metal walls: Status of the lithium tokamak experiment". Fusion Engineering and Design. 85 (6): 874–881. Bibcode:2010FusED..85..874K. doi:10.1016/j.fusengdes.2010.04.005. OSTI 973198. S2CID 120010130.