The Tritium Systems Test Assembly (TSTA) was a facility at
Los Alamos National Laboratory dedicated to the development and demonstration of technologies required for
fusion-relevant
deuterium-
tritium processing. Facility design was launched in 1977. It was commissioned in 1982, and the first
tritium was processed in 1984. The maximum tritium inventory was 140 grams.[1][2][3][4][5][6][7]
References
^Anderson, J. L., T. Naito, et al. (1988). "Experience of TSTA milestone runs with 100 grams-level of tritium." Fusion Technology 14(2): 438-443.
^Bartlit, J. R., J. L. Anderson, et al. (1983). Subsystem Cost Data for the Tritium Systems Test Assembly. 10th
Symposium on
Fusion Engineering, Philadelphia.
^Sherman, R. H., J. R. Bartlit, et al. (1988). "Operation of the TSTA
Isotope Separation System with 100 Gram Tritium." Fusion Technology 14(2): 1273-1276.
^Willms, R. S. and K. Okuno; "Recovery of
Hydrogen from Impurities Using a
PalladiumMembrane Reactor", Proceedings of the 15th IEEE Symposium on Fusion Engineering, Hyannis, Massachusetts, 85-90, October 11–15, 1993.
^Konishi, S., R. S. Willms, et al.; "Extended Operation of Reactor-Scale Fusion Fuel Loop Under US-Japan Collaboration"; Proceedings of the 15th IEEE Symposium on Fusion Engineering, Hyannis, Massachusetts, 204-207, October 11–15, 1993.
^Willms, R.S., K. Kobayashi, Y. Iwai, T. Hayashi, S. O'hira, M. Nishi, D. Hyatt and R.V. Carlson; "Behavior of tritium in the TSTA test cell combined with operation of the Experimental Tritium Cleanup (ETC) system";
Fusion Engineering and Design, 61-62, 575 - 583 (2002).
The Tritium Systems Test Assembly (TSTA) was a facility at
Los Alamos National Laboratory dedicated to the development and demonstration of technologies required for
fusion-relevant
deuterium-
tritium processing. Facility design was launched in 1977. It was commissioned in 1982, and the first
tritium was processed in 1984. The maximum tritium inventory was 140 grams.[1][2][3][4][5][6][7]
References
^Anderson, J. L., T. Naito, et al. (1988). "Experience of TSTA milestone runs with 100 grams-level of tritium." Fusion Technology 14(2): 438-443.
^Bartlit, J. R., J. L. Anderson, et al. (1983). Subsystem Cost Data for the Tritium Systems Test Assembly. 10th
Symposium on
Fusion Engineering, Philadelphia.
^Sherman, R. H., J. R. Bartlit, et al. (1988). "Operation of the TSTA
Isotope Separation System with 100 Gram Tritium." Fusion Technology 14(2): 1273-1276.
^Willms, R. S. and K. Okuno; "Recovery of
Hydrogen from Impurities Using a
PalladiumMembrane Reactor", Proceedings of the 15th IEEE Symposium on Fusion Engineering, Hyannis, Massachusetts, 85-90, October 11–15, 1993.
^Konishi, S., R. S. Willms, et al.; "Extended Operation of Reactor-Scale Fusion Fuel Loop Under US-Japan Collaboration"; Proceedings of the 15th IEEE Symposium on Fusion Engineering, Hyannis, Massachusetts, 204-207, October 11–15, 1993.
^Willms, R.S., K. Kobayashi, Y. Iwai, T. Hayashi, S. O'hira, M. Nishi, D. Hyatt and R.V. Carlson; "Behavior of tritium in the TSTA test cell combined with operation of the Experimental Tritium Cleanup (ETC) system";
Fusion Engineering and Design, 61-62, 575 - 583 (2002).