Analysis of tritium permeation in the steam generators of the SEAFP/SEAL fusion power reactor

摘要

The key uncertainty in estimating tritium permeation from fusion reactor cooling system components is the permeability coefficient, which is strongly dependent on the component material, pressure, temperature, chemistry, etc. Published tritium permeability values, for typical cooling system materials, range at least six orders of magnitude, resulting in estimates of tritium permeation carrying a large degree of uncertainty. In this work, both theoretical and empirical approaches are used for estimating tritium permeation and environmental releases for the water cooled SEAFP reactor. The steam generators are the major source of tritium permeation from the primary coolant.