Now showing items 1-4 of 4
Investigation of NdxY0.25–xZr0.75O1.88 inert matrix fuel materials made by a co-precipitation synthetic route
(NRC Research Press, 2016)
Yttria-stabilized zirconia (YSZ) is a material that is being considered for use as an inert matrix fuel in nuclear reactors, but a complete characterization of these materials is required for them to be licensed for use. ...
An investigation of the thermal stability of NdxYyZr1 x yO2 d inert matrix fuel materials
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 ...
Investigating the Geochemical Model for Molybdenum Mineralization in the JEB Tailings Management Facility at McClean Lake, Saskatchewan: An X‐ray Absorption Spectroscopy Study
(American Chemical Society, 2015)
The geochemical model for Mo mineralization in the JEB Tailings Management Facility (JEB TMF), operated by AREVA Resources Canada at McClean Lake, Saskatchewan, was investigated using X-ray Absorption Near-Edge Spectroscopy ...
Investigation of the Thermal Stability of NdxScyZr1−x−yO2−δ Materials Proposed for Inert Matrix Fuel Applications
(American Chemical Society, 2016)
Inert matrix fuels (IMF) consist of transuranic elements (i.e., Pu, Am, Np, Cm) embedded in a neutron transparent (inert) matrix and can be used to “burn up” (transmute) these elements in current or Generation IV nuclear ...