References
- A. WIDDOWSON et al., “Evaluation of Tritium Retention in Plasma Facing Components During JET Tritium Operations,” Phys. Scr., 96, 12, 8 (2021); https://doi.org/10.1088/1402-4896/ac3b30.
- A. WIDDOWSON et al., “Overview of Fuel Inventory in JET with ITER-Like Wall,” Nucl. Fusion, 57, 8, 086045 (2017); https://doi.org/10.1088/1741-4326/aa7475.
- M. KRESINA et al., “Preparation for Commissioning of Materials Detritiation Facility at Culham Science Centre,” Fusion Eng. Des., 136, 1391 (2018); https://doi.org/10.1016/j.fusengdes.2018.05.019.
- C. TOMASTIK, W. WERNER, and H. STORI, “Oxidation of Beryllium—A Scanning Auger Investigation,” Nucl. Fusion, 45, 9, 1061 (2005); https://doi.org/10.1088/0029-5515/45/9/005.
- J. HABAINY and C. NILSSON, “Oxidation of Pure Tungsten in the Temperature Interval 400° to 900℃,” Lund University (2013).
- P. PACENTI, R. EDWARDS, and F. CAMPI, “Detritiation of Graphite and Beryllium Plasma Facing Components,” Proc. 19th Symp. Fusion Technology – Fusion Technology 1996, Lisbon, Portugal, September 16–20, 1996, p. 1705, North-Holland (1996).
- L. AVOTINA et al., “Thermal Desorption of Hydrogen Isotopes from the JET Be Plasma Facing Components,” Phys. Scr., T171, 014009 (2020).
- X. YE et al., “Determination of the Detrapping Energy of Tritium in Tungsten,” J. Nucl. Mater., 544, 152662 (2021).
- “Saving Time on the Way to ITER Operation,” ITER Newsline (May 15, 2017); https://www.iter.org/newsline/-/2722.
- S. ATZENI and J. MAYER-TER-VEHN, The Physics of Inertial Fusion, Oxford University Press (2009).
- S. REYNOLDS, “Materials Detritiation Facility Process Management and Achieved Detritiation Factors,” EUROfusion (2019).