Radiation protection potential of MOX-fuel doped with 231Pa and Cs radioisotopes

Abstract

The paper addresses the problem of MOX-fuel self-protection during full cycle of MOX-fuel management. Under conditions of the closed LWR cycle the proliferation-resistance levels were evaluated for fresh and spent MOX-fuel with 231Pa and Cs feed. As it follows from the paper results, combination of these two admixtures being doped into MOX-fuel is able to enhance the inherent radiation barrier and to weaken shortcomings of both proliferation deterrents.

Dissolution of mixed oxide(MOX) fuel in nitric acid:A review

“…Within the realm of fast reactors, uranium ceramic and metal fuels represent the primary categories employed internationally. Remarkably, mixed oxide (MOX) fuel, comprising uranium dioxide (UO 2 ) and plutonium dioxide (PuO 2 ) [ 7 , 8 ], emerges as the most prevalent and well-established fuel type [ [9] , [10] , [11] , [12] ]. In the context of the fast reactor fuel cycle, efficient reprocessing of spent fuel becomes imperative for the expeditious recovery of plutonium from the aforementioned spent fuel.…”