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E 1.99:wsrc-ms-2002-01022
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Evaluating Residence Time for Cesium Removal from Simulated Hanford Tank Wastes Using SuperLig(R) 644 Resin |
1 |
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E 1.99:wsrc-ms-2002-01025, rev. 1
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Radiochemical Separations for the Pretreatment of High Level Nuclear Wastes at the Savannah River Site |
2 |
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E 1.99:wsrc-ms-2003-00016
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Improved Methodology Application for 12-Rad Analysis in a Shielded Facility at SRS |
1 |
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E 1.99:wsrc-ms-2003-00050
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Radioactive Waste Evaporation Current Methodologies Employed for the Development, Design, and Operation of Waste Evaporators at the Savannah River Site and Hanford Waste Treatment Plant. |
1 |
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E 1.99:wsrc-ms-2003-00053
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The Savannah River Site Accelerated Cleanup Mission Sludge Retrieval and Immobilization. |
1 |
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E 1.99:wsrc-ms-2003-00071
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Computational and Experimental Analysis of the Effectiveness of the Argon Reservoir |
1 |
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E 1.99:wsrc-ms-2003-00072
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Offgas Emissions from the Vitrification of Hanford Envelope C Low Activity Waste |
1 |
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E 1.99:wsrc-ms-2003-00076
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Challenges of Non-Destructive Assay Waste Measurement |
1 |
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E 1.99:wsrc-ms-2003-00084
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Assessment of Ivanpah Playa as a Site for Thermal Vicarious Calibration for the MTI Satellite |
1 |
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E 1.99:wsrc-ms-2003-00085
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Implementation of an Outer Can Welding System for Savannah River Site FB-Line |
1 |
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E 1.99:wsrc-ms-2003-00088
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Effects of Point Sources in Trench Disposal of Radioactive Waste |
1 |
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E 1.99:wsrc-ms-2003-00089, rev. 1
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Demonstration of the UREX Solvent Extraction Process with Dresden Reactor Fuel |
1 |
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E 1.99:wsrc-ms-2003-00090
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Hydrogen Absorption Property of Encapsulated Lani4.25A10.75 |
1 |
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E 1.99:wsrc-ms-2003-00091
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Simulation of a Batch Chemical Process Using Parallel Computing with PVM and Speedup |
1 |
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E 1.99:wsrc-ms-2003-00099
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A Comparison of the Daphnids, Ceriodaphnia dubia and Daphnia ambigua, for their Utilization in Routine Toxicity Testing in the Southeastern United States |
1 |
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E 1.99:wsrc-ms-2003-00102
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HB-Line Material Control and Accountability Measurements at SRS |
1 |
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E 1.99:wsrc-ms-2003-00104
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Post Fire Transient Temperature Distribution in Drum Type Package in Absence of Heat |
1 |
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E 1.99:wsrc-ms-2003-00105
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Dissolution of Dresden Reactor Fuel |
1 |
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E 1.99:wsrc-ms-2003-00110
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Hanford Sr/TRU Decontamination Program Research from Beaker to Pilot Scale. |
1 |
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E 1.99:wsrc-ms-2003-00113
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Crack Growth Behavior in Residual Stress Field in Vessel Type Structures |
1 |
