An investigation of the thermal stability of Nd Y Zr1−−O2− inert matrix fuel materials

摘要: Abstract An important step in achieving a closed uranium fuel cycle is to develop new inert matrix (IMF) materials for use the burn-up of transuranic species (TRU; i.e., Pu, Np, Am, Cm). Cubic fluorite zirconia (ZrO 2 ) has ideal properties IMF applications, but it not stable at room temperature and must be stabilized through addition small amounts dopants such as Y. While Y-substituted (YSZ) been extensively studied, relatively little work done investigate how an actinide YSZ system affects these materials. To this end, long-range local structures series Nd x Y y Zr 1 − O δ compounds (Nd was used surrogate Am) were studied using powder X-ray diffraction (XRD), scanning electron microscopy (SEM), absorption spectroscopy (XAS) K-, L 3 -, -edges. The thermal stability Nd–YSZ also investigated by annealing temperatures ranging between 600 1400 °C. These studies showed that 1− improved (i.e. ⩾5 at.%) system. Additionally, XAS results structure around remained constant; only changes second coordination shell observed when annealed. strongly suggest can significantly improve zirconia-based IMFs. This study confirmed importance value advanced characterization techniques are sensitive material (i.e., XAS).