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

Nuclear Fuels & Materials

Research output: Contribution to journal › Conference article › peer-review

42 Scopus citations

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
State	Published - Aug 1 2004
Event	Proceedings of the 11th Conference on Fusion Research - Kyoto, Japan Duration: Dec 7 2003 → Dec 12 2003

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@article{e922041e42c140bf8877c31874f34bd2,

title = "Deuterium/tritium behavior in Flibe and Flibe-facing materials",

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",

note = "Funding Information: This work was supported partially by the US Department of Energy, Office of Sciences, and by the Japan–US joint research program, JUPITER-II, under the DOE Idaho Operations Contract DE-AC07-99ID13727.; Proceedings of the 11th Conference on Fusion Research ; Conference date: 07-12-2003 Through 12-12-2003",

year = "2004",

month = aug,

day = "1",

doi = "10.1016/j.jnucmat.2004.04.220",

language = "English",

volume = "329-333",

pages = "1327--1331",

journal = "Journal of Nuclear Materials",

issn = "0022-3115",

publisher = "Elsevier B.V.",

number = "1-3 PART B",

}

TY - JOUR

T1 - Deuterium/tritium behavior in Flibe and Flibe-facing materials

AU - Anderl, R. A.

AU - Fukada, S.

AU - Smolik, G. R.

AU - Pawelko, R. J.

AU - Schuetz, S. T.

AU - Sharpe, J. P.

AU - Merrill, B. J.

AU - Petti, D. A.

AU - Nishimura, H.

AU - Terai, T.

AU - Tanaka, S.

N1 - Funding Information: This work was supported partially by the US Department of Energy, Office of Sciences, and by the Japan–US joint research program, JUPITER-II, under the DOE Idaho Operations Contract DE-AC07-99ID13727.

PY - 2004/8/1

Y1 - 2004/8/1

N2 - 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.

AB - 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.

UR - https://www.scopus.com/pages/publications/3342914826

U2 - 10.1016/j.jnucmat.2004.04.220

DO - 10.1016/j.jnucmat.2004.04.220

M3 - Conference article

AN - SCOPUS:3342914826

SN - 0022-3115

VL - 329-333

SP - 1327

EP - 1331

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

IS - 1-3 PART B

T2 - Proceedings of the 11th Conference on Fusion Research

Y2 - 7 December 2003 through 12 December 2003

ER -

Deuterium/tritium behavior in Flibe and Flibe-facing materials

Abstract

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