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Schwartz, Daniel S

Publications and source records attributed to Schwartz, Daniel S.

Application of Micro-XRF for Nuclear Materials Characterization and Problem Solving

Micro-X-ray fluorescence (MXRF) used for >> 20 years To date MXRF has been underutilized for nuclear materials (NM) spatially-resolved elemental characterization. Scanning electron microscopy (SEM) with EDX much more common for NM characterization at a micro scale. But MXRF fills gap for larger 10's microns to cm{sup 2} scales. Will present four interesting NM applications using MXRF. Demonstrated unique value of MXRF for various plutonium applications. Although SEM has much higher resolution, MXRF clearly better for these larger scale samples (especially non-conducting samples). MXRF useful to quickly identify insoluble particles in Pu/Np oxide. MXRF vital to locating HEPA filter Pu particles over cm{sup 2} areas which were then extracted for SEM morphology and particle size distribution analysis. MXRF perfect for surface swipes which are far too large for practical SEM imaging, and loose residue would contaminate SEM vacuum chamber. MXRF imaging of ER Plutonium metal warrants further studies to explore metal elemental heterogeneity.

37 INORGANIC, ORGANIC, PHYSICAL, AND ANALYTICAL CH↗

Properties of Liquid Plutonium

Unalloyed polycrystalline Pu displays extreme thermal expansion behavior, i.e., {alpha} {yields} {beta} {yields} {gamma} {yields} {delta} increases by 25% in volume and {delta} {yields} {var_epsilon} {yields} liquid decreases by 4.5% in volume. Thus, making it difficult to measure density into the liquid state. Dilatometer outfitted with CaF molten metal cell offers a proven capability to measure thermal expansion in molten metals, but has yet to be proven for Pu. Historic data from the liquid nuclear fuels program will prove extremely useful as a guide to future measurements. 3.3at% Ga changes Pu molten metal properties: 50% increase in viscosity and {approx}3% decrease in density. Fe may decrease the density by a small amount assuming an averaging of densities for Pu-Ga and Pu-Fe liquids. More recent Boivineau (2009) work needs some interpretation, but technique is being employed in (U,Pu)O{sub 2} nuclear fuels program (Pu Futures, 2012).

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS↗