“…While standard U-Pu MOX options have been considered (Gul, et al, 2018) (Salam & Hah, 2018) (Alonso, et al, 2018) (Ramirez, et al, 2016) (Haas & Hamilton, 2007) (Cowell & Fisher, 1999) (Schlosser, et al, 1993), studies have shown that Th-Pu MOX may provide a promising alternative (Ernoult, et al, 2015) (Lau, et al, 2014) (Revol, et al, 2013) (National Nuclear Laboratory, 2012 (Fridman & Kliem, 2011) (International Atomic Energy Agency, 2005) (International Atomic Energy Agency, 2002) (Galperin, 1995) (Cadelli & Lippens, 1988) (Shapiro, et al, 1977). The high conversion ratio and lack of breeding of additional Pu in the Th-cycle results in significantly lower Pu / MA content in discharged fuel compared to standard U-Pu MOX, leading to potentially lower levels of radiotoxicity and decay heat of associated waste materials compared to standard UO2 and U-Pu fuels (Hesketh & Thomas, 2013) (International Atomic Energy Agency, 2005).…”