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E 1.99:14-6311
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SiC-ODS Alloy Gradient Nanocomposites as Novel Cladding Materials |
1 |
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E 1.99:14--6346
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Integrated Computational Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709 |
1 |
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E 1.99:14-6357 doe-clemson--08260
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Final Project Report CFA-14-6357 A New Paradigm for Understanding Multiphase Ceramic Waste Form Performance. |
1 |
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E 1.99:14--6377
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Selectivity in Ligand Binding to Uranyl Compounds A Synthetic, Structural, Thermodynamic and Computational Study. |
1 |
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E 1.99:14-6378
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Improved Hybrid Modeling of Spent Fuel Storage Facilities |
1 |
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E 1.99:14-6472
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Computational and Experimental Studies of Microstructure-Scale Porosity in Metallic Fuels for Improved Gas Swelling Behavior |
1 |
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E 1.99:14-6482
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Studies of Lanthanide Transport in Metallic Fuel |
1 |
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E 1.99:14-6489
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Rare Earth Electrochemical Property Measurements and Phase Diagram Development in a Complex Molten Salt Mixture for Molten Salt Recycle |
1 |
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E 1.99:14--6542
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Development and Optimization of Voltammetric Methods for Real Time Analysis of Electrorefiner Salt with High Concentrations of Actinides and Fission Products |
1 |
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E 1.99:14-6552
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High-resolution time-resolved experiments on mixing and entrainment of buoyant jets in stratified environments |
1 |
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E 1.99:14--6557
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Extraction of Uranium from Seawater Design and Testing of a Symbiotic System. |
1 |
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E 1.99:14-6557
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Extraction of Uranium from Seawater Design and Testing of a Symbiotic System. |
1 |
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E 1.99:14-6604
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Development of high performance ODS alloys |
1 |
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E 1.99:14--6670
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Fundamental study of key issues related to advanced sCO<sub>2</sub> Brayton cycle Prototypic HX development and cavitation. |
1 |
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E 1.99:14-6700 ebr2-lmfr-resr--001
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EBR-II Reactor Physics Benchmark Evaluation Report |
1 |
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E 1.99:14-6702
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Combining Experiments and Simulations of Extraction Kinetics and Thermodynamics in Advanced Separation Processes for Used Nuclear Fuel |
1 |
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E 1.99:14-6762
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Fundamental Studies of Irradiation-Induced Modifications in Microstructural Evolution and Mechanical Properties of Advanced Alloys |
1 |
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E 1.99:14-6767
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Thermal Conductivity of Metallic Uranium |
1 |
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E 1.99:14-6770
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(Project 14-6770) An Investigation to Establish Multiphysical Property Dataset of Nuclear Materials Based on in-situ Observations and Measurements |
1 |
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E 1.99:14--6782
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Development and Deployment Assessment of a Melt-Down Proof Modular Micro Reactor (MDP-MMR) |
1 |
