Evaluation of mitigation strategies for radioactive fission gases in fluoride-salt-cooled high-temperature reactors

Author:

Zhang Sheng,Sun Xiaodong

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference53 articles.

1. Tritium permeation through clean construction alloys;Bell;J. Mater. Energy Syst.,1979

2. Tritium in molten-salt reactors;Briggs;Reactor Technol.,1971

3. Calderoni, P., Ebner, M., “Hydrogen Permeability of Incoloy 800H, Inconel 617, and Haynes 230 Alloys,” INL/EXT-10-19387, Idaho National Laboratory (2010).

4. Calderoni, P., Sharpe, P., Hara, M., Oya, Y., “Measurement of Tritium Permeation in FLiBe (2LiF-BeF2)”, INL/CON-07-13267, Idaho National Laboratory (2007).

5. Cantor, S., “Density and Viscosity of Several Molten Fluoride Mixtures,” ORNL/TM-4308, Oak Ridge National Laboratory (1973).

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