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An investigation of the thermal stability of NdxYyZr1 x yO2 d inert matrix fuel materials
(Elsevier, 2015)
An important step in achieving a closed uranium fuel cycle is to develop new inert matrix fuel (IMF) materials for use in the burn-up of transuranic species (TRU; i.e., Pu, Np, Am, Cm). Cubic fluorite zirconia (ZrO2) has ...