Laser-Induced Ablation and Desorption of Deuterium-Containing Tungsten Films

封面

如何引用文章

全文:

开放存取 开放存取
受限制的访问 ##reader.subscriptionAccessGranted##
受限制的访问 订阅存取

详细

The laser-induced desorption (LID) and laser-induced ablation (LIA) methods are compared with each other regarding the possibility of measurements an absolute quantitative analysis of hydrogen isotopes content in first wall materials of fusion reactors. Deuterium containing tungsten films with a thickness of 300–400 nm on a silicon substrate were used as model samples. To implement the LID, the samples were irradiated with laser pulses with a duration of 200 microseconds and an energy density of 50–150 J/cm2, for LIA – 12 ns and 5–15 J/cm2. The registration of residual gases was carried out by quadrupole mass spectrometry. Computer simulation of laser pulse heating was performed for the LID process. The simulation results and experimental data showed that heating at an energy density of 100–150 J/cm2 is sufficient to degas tungsten films of the studied thickness. A comparison of the amount of desorbed deuterium in the LID (150 J/cm2) and LIA (15 J/cm2) modes shows that it is identical within the measurement error and is equal to 4.15±0.15·1014 cm-2.

作者简介

E. Smirnova

A.F. Ioffe Physicotechnical Institute, Russian Academy of Sciences; Saint Petersburg State University

编辑信件的主要联系方式.
Email: evsmirnova@mail.ioffe.ru
俄罗斯联邦, Saint Petersburg; Saint Petersburg

O. Medvedev

A.F. Ioffe Physicotechnical Institute, Russian Academy of Sciences; MEPhI National Research Nuclear University

Email: evsmirnova@mail.ioffe.ru
俄罗斯联邦, Saint Petersburg; Moscow

A. Razdobarin

A.F. Ioffe Physicotechnical Institute, Russian Academy of Sciences; Saint Petersburg State University

Email: evsmirnova@mail.ioffe.ru
俄罗斯联邦, Saint Petersburg; Saint Petersburg

D. Elets

A.F. Ioffe Physicotechnical Institute, Russian Academy of Sciences; MEPhI National Research Nuclear University; Saint Petersburg State University

Email: evsmirnova@mail.ioffe.ru
俄罗斯联邦, Saint Petersburg; Moscow; Saint Petersburg

L. Snigirev

A.F. Ioffe Physicotechnical Institute, Russian Academy of Sciences; Saint Petersburg State University

Email: evsmirnova@mail.ioffe.ru
俄罗斯联邦, Saint Petersburg; Saint Petersburg

Ya. Shubin

A.F. Ioffe Physicotechnical Institute, Russian Academy of Sciences; Saint Petersburg State University

Email: evsmirnova@mail.ioffe.ru
俄罗斯联邦, Saint Petersburg; Saint Petersburg

参考

  1. Mukhin E.E. et al. In situ monitoring hydrogen isotope retention in ITER first wall // Nuclear Fusion. 2016. V. 56. № 3. P. 036017. https://doi.org/10.1088/0029-5515/56/3/036017
  2. Roth J. et al. Tritium inventory in ITER plasma-facing materials and tritium removal procedures // Plasma Physics and Controlled Fusion. 2008. V. 50. № 10. P. 103001. https://doi.org/10.1088/0741-3335/50/10/103001
  3. Родина Н.Д., Морозова Н.Б., Введенский А.В. Кинетика выделения атомарного водорода и водородопроницаемость сплавов Ag-Pd в щелочной среде // Конденсированные среды и межфазные границы. 2020. Т. 22. № 2. С. 96–104. https://doi.org/10.17308/kcmf.2020.22/2853
  4. Dellasega D. et al. Deuterium retention and surface modifications of nanocrystalline tungsten films exposed to high-flux plasma // J. Nuclear Materials. 2015. V. 463. P. 989–992. doi: 10.1016/j.jnucmat.2014.11.025
  5. Skinner C.H. Tritium retention and removal in Tokamaks // AIP Conference Proc. American Institute of Physics, 2009. V. 1095. № 1. P. 127–145. https://doi.org/doi: 10.1063/1.3097310
  6. Krat S.A. et al. A setup for study of co-deposited films // J. Instrumentation. 2020. V. 15. № 1. P. P01011. https://doi.org/10.1088/1748-0221/15/01/P01011
  7. Rubel M. et al. Efficiency of fuel removal techniques tested on plasma-facing components from the TEXTOR tokamak // Fusion Engineering and Design. 2012. V. 87. № 5–6. P. 935–940. https://doi.org/10.1016/j.fusengdes.2012.02.054
  8. Katayama K., Nishikawa M., Yamaguchi J. Isotope effect in hydrogen isotope exchange reaction on first wall materials // J. Nuclear Science and Technology. 2002. V. 39. № 4. P. 371–376. https://doi.org/10.1080/18811248.2002.9715206
  9. Hodille E.A. et al. Retention and release of hydrogen isotopes in tungsten plasma-facing components: the role of grain boundaries and the native oxide layer from a joint experiment-simulation integrated approach // Nuclear Fusion. 2017. V. 57. № 7. P. 076019. https://doi.org/10.1088/1741-4326/aa6d24
  10. Moshkunov K.A. et al. Air exposure and sample storage time influence on hydrogen release from tungsten // J. Nuclear Materials. 2010. V. 404. № 3. P. 174–177. https://doi.org/10.1016/j.jnucmat.2010.07.011
  11. Zlobinski M. et al. Laser induced desorption as tritium retention diagnostic method in ITER // Fusion Engineering and Design. 2011. V. 86. № 6–8. P. 1332–1335. https://doi.org/10.1016/j.fusengdes.2011.02.030
  12. Paris P. et al. Comparison of LIBS results on ITER-relevant samples obtained by nanosecond and picosecond lasers // Nuclear Materials and Energy. 2019. V. 18. P. 1–5. https://doi.org/10.1016/j.nme.2018.11.018
  13. Maddaluno G. et al. Detection by LIBS of the deuterium retained in the FTU toroidal limiter // Nuclear Materials and Energy. 2019. V. 18. P. 208–211. https://doi.org/10.1016/j.nme.2018.12.029
  14. Gierse N. et al. In situ characterisation of hydrocarbon layers in TEXTOR by laser induced ablation and laser induced breakdown spectroscopy // J. Nuclear Materials. 2011. V. 415. № 1. P. S1195–S1198. https://doi.org/10.1016/j.jnucmat.2010.11.055
  15. Van Der Meiden H.J. et al. Monitoring of tritium and impurities in the first wall of fusion devices using a LIBS based diagnostic // Nuclear Fusion. 2021. V. 61. № 12. P. 125001. https://doi.org/10.1088/1741-4326/ac31d6
  16. Razdobarin G.T. et al. Detecting dust on plasma-facing components in a next-step tokamak using a laser-induced breakdown spectroscopy technique // Fusion Science and Technology. 2002. V. 41. № 1. P. 32–43. https://doi.org/10.13182/FST02-A198
  17. Liu J. et al. Study of spectral intensity of the laser ablated tungsten plasma and ablation mass at various laser spot sizes and laser fluence in vacuum environment // Spectrochimica Acta Part B: Atomic Spectroscopy. 2023. V. 199. P. 106569. https://doi.org/10.1016/j.sab.2022.106569
  18. Zhang D.L. Processing of advanced materials using high-energy mechanical milling // Progress in Materials Science. 2004. V. 49. № 3–4. P. 537–560. https://doi.org/10.1016/S0079-6425(03)00034-3
  19. Yehia-Alexe S.A. et al. Considerations on hydrogen isotopes release from thin films by laser induced ablation and laser induced desorption techniques // Spectrochimica Acta Part B: Atomic Spectroscopy. 2023. V. 208. P. 106774. https://doi.org/10.1016/j.sab.2023.106774
  20. Zlobinski M. et al. Laser-Induced Desorption of co-deposited Deuterium in Beryllium Layers on Tungsten // Nuclear Materials and Energy. 2019. V. 19. P. 503–509. https://doi.org/10.1016/j.nme.2019.04.007
  21. Krat S. et al. Tungsten-deuterium co-deposition: Experiment and analytical description // Vacuum. 2018. V. 149. P. 23–28. https://doi.org/10.1016/j.vacuum.2017.12.004
  22. Kajita S. et al. Plasma-assisted laser ablation of tungsten: Reduction in ablation power threshold due to bursting of holes/bubbles // Applied Physics Letters. 2007. V. 91. №. 26. https://doi.org/10.1063/1.2824873

补充文件

附件文件
动作
1. JATS XML

版权所有 © Russian Academy of Sciences, 2024