Optical transfer interfaces for FTIR spectroscopy on irradiated nuclear reactor components

Corrosion is one of the factors limiting the life expectancy of zirconium alloy components irradiated in nuclear power reactors. A non-destructive and rapid means of measuring corrosion film thickness on spent fuel-element cladding and on pressure tubes removed from CANDU power reactors is required by the nuclear industry. The authors have designed and fabricated optical interfaces for a Fourier Transform Infrared (FTIR) spectrometer that uses the reflection mode to obtain interference spectra from the surfaces of fuel elements and pressure tubes. These components are stored in inspection pools, under four to six meters of water, or in hot cells, behind nearly a meter of concrete and lead glass shielding. This paper describes the optical design of the interfaces, specimen holding assemblies, and successful testing of the optical assemblies