Diffusion coefficients of hydrogen isotopes in Flibe were correlated with making reference to previous relating data of F ion self-diffusivity and Flibe viscosity and so on. Rates of tritium permeation through structural materials in a fusion reactor system with Flibe blanket were estimated comparatively under conditions with or without a Flibe permeation barrier. A way to lower the tritium leak rate below a level regulated by law was proposed, and its effectiveness was discussed.
All Science Journal Classification (ASJC) codes
- Civil and Structural Engineering
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Materials Science(all)
- Mechanical Engineering