Deuterium/tritium behavior in Flibe and Flibe-facing materials

R. A. Anderl; S. Fukada; G. R. Smolik; R. J. Pawelko; S. T. Schuetz; J. P. Sharpe; B. J. Merrill; D. A. Petti; H. Nishimura; T. Terai; S. Tanaka

doi:10.1016/j.jnucmat.2004.04.220

Deuterium/tritium behavior in Flibe and Flibe-facing materials

R. A. Anderl, S. Fukada, G. R. Smolik, R. J. Pawelko, S. T. Schuetz, J. P. Sharpe, B. J. Merrill, D. A. Petti, H. Nishimura, T. Terai, S. Tanaka

Engineering Science for Advanced energy system

Research output: Contribution to journal › Conference article

26 Citations (Scopus)

Abstract

Experimental studies to investigate the behavior of deuterium and tritium in the molten salt Flibe (2LiF·BeF₂), have been conducted as part of the Japan-US joint research program (JUPITER-II). Measurements of deuterium transport were made in a cylindrically symmetric, dual permeation probe assembly containing 400 cc of Flibe. An exact analytical transport solution in cylindrical coordinates was fit to the measured permeation data, and this analysis derived deuterium diffusion and solubility coefficients of 8.0×10^-10 m²/s and 3.1×10^-4 mol/m³Pa at 600 °C, respectively, and 3.0×10^-9 m²/s and 1.0×10^-4 mol/m³Pa at 650 °C. The diffusion coefficients were about a factor of two less than previous results derived from capillary-reservoir diffusion measurements with tritium. Solubility results were significantly greater than previously measured for D₂ but they were comparable to those for DF in Flibe. The results suggest that the dominant deuterium transport species in Flibe was D ⁺F^- for these experiments.

Original language	English
Pages (from-to)	1327-1331
Number of pages	5
Journal	Journal of Nuclear Materials
Volume	329-333
Issue number	1-3 PART B
DOIs	https://doi.org/10.1016/j.jnucmat.2004.04.220
Publication status	Published - Aug 1 2004
Event	Proceedings of the 11th Conference on Fusion Research - Kyoto, Japan Duration: Dec 7 2003 → Dec 12 2003

All Science Journal Classification (ASJC) codes

Nuclear and High Energy Physics
Materials Science(all)
Nuclear Energy and Engineering

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Anderl, R. A., Fukada, S., Smolik, G. R., Pawelko, R. J., Schuetz, S. T., Sharpe, J. P., Merrill, B. J., Petti, D. A., Nishimura, H., Terai, T., & Tanaka, S. (2004). Deuterium/tritium behavior in Flibe and Flibe-facing materials. Journal of Nuclear Materials, 329-333(1-3 PART B), 1327-1331. https://doi.org/10.1016/j.jnucmat.2004.04.220

Deuterium/tritium behavior in Flibe and Flibe-facing materials. / Anderl, R. A.; Fukada, S.; Smolik, G. R.; Pawelko, R. J.; Schuetz, S. T.; Sharpe, J. P.; Merrill, B. J.; Petti, D. A.; Nishimura, H.; Terai, T.; Tanaka, S.

In: Journal of Nuclear Materials, Vol. 329-333, No. 1-3 PART B, 01.08.2004, p. 1327-1331.

Research output: Contribution to journal › Conference article

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abstract = "Experimental studies to investigate the behavior of deuterium and tritium in the molten salt Flibe (2LiF·BeF2), have been conducted as part of the Japan-US joint research program (JUPITER-II). Measurements of deuterium transport were made in a cylindrically symmetric, dual permeation probe assembly containing 400 cc of Flibe. An exact analytical transport solution in cylindrical coordinates was fit to the measured permeation data, and this analysis derived deuterium diffusion and solubility coefficients of 8.0×10-10 m2/s and 3.1×10-4 mol/m3Pa at 600 °C, respectively, and 3.0×10-9 m2/s and 1.0×10-4 mol/m3Pa at 650 °C. The diffusion coefficients were about a factor of two less than previous results derived from capillary-reservoir diffusion measurements with tritium. Solubility results were significantly greater than previously measured for D2 but they were comparable to those for DF in Flibe. The results suggest that the dominant deuterium transport species in Flibe was D +F- for these experiments.",

author = "Anderl, {R. A.} and S. Fukada and Smolik, {G. R.} and Pawelko, {R. J.} and Schuetz, {S. T.} and Sharpe, {J. P.} and Merrill, {B. J.} and Petti, {D. A.} and H. Nishimura and T. Terai and S. Tanaka",

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