Passive gamma-ray scanning for non-destructive characterisation of mixed oxide (MOX) fuel pins for BWRs

Non destructive determination of PuO2 content in MOX fuel pins for fast reactors using Passive Gamma Scanning

“…Scanning the fuel rods through a Cs 137 gamma densitometer and/or assaying a nuclide using fission gammas and delayed neutrons by using a Cf 252 neutron source is also reported [10]. Use of PGS has been demonstrated for estimating the PuO 2 content in MOX fuel pins for thermal reactors with PuO 2 content (0.9-3.25%) [11]. PGS has also been demonstrated for calculating the fissile column length in Mixed Carbide fuel pins with 70% PuC for FBTR [12].…”