Plasma and Fusion Research
Volume 14, 1405044 (2019)
Regular Articles
- 1)
- SOKENDAI (The Graduate University for Advanced Studies), Toki 509-5292, Japan
- 2)
- National Institute for Fusion Science, Toki 509-5292, Japan
- 3)
- Institute of Advanced Energy, Kyoto University, Uji 611-0011, Japan
- 4)
- Graduate School of Engineering, Osaka University, Suita 565-0871, Japan
- 5)
- Interdisciplinary Graduate School of Engineering Science, Kyushu University, Kasuga 816-8580, Japan
Abstract
Release behaviors of tritium from molten FLiNaBe (LiF–NaF–BeF2) have been examined in a series of low flux neutron irradiation experiments with an AmBe neutron source at the OKTAVIAN facility of Osaka University. Tritium released from FLiNaBe is swept by He and Ar gases, and recovered by water bubblers. The recovery rate of tritium released from 300 cm3 of FLiNaBe was 58.0 mBq/h in a steady state, and it was close to the tritium production rate of 58.0 mBq/h calculated by the MCNP6 code. The values of the overall mass transfer coefficients for tritium release from FLiNaBe were close to those for FLiNaK (LiF–NaF–KF) at 773 K. The influence of the diffusivity and the solubility of tritium on the overall mass transfer coefficients has been examined on molten FLiNaBe.
Keywords
FLiNaBe, molten salt, AmBe neutron source, low flux neutron, tritium recovery
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