Call Number (LC) Title Results
E 1.99:wsrc-tr-2002-00052 Characterization of Tank 19 Residual Waste 1
E 1.99:wsrc-tr-2002-00052, rev. 1 Characterization of Tank 19 Residual Waste 1
E 1.99:wsrc-tr-2002-00054 Potential for the Precipitation of Uranium and Plutonium Solids upon Addition of Nitric Acid to Waste Solutions in a Caustic-Side Solvent Extraction Process 1
E 1.99:wsrc-tr-2002-00055 SRTC Spreadsheet to Determine Relative Percent Difference (RPD) for Duplicate Waste Assay Results and to Perform the RPD Acceptance Test 1
E 1.99:wsrc-tr-2002-00057 2000 Savannah River Biological Surveys for Westinghouse Savannah River Company 1
E 1.99:wsrc-tr-2002-00058 SRTC Offgas Data from Formic Acid Addition to the Sludge Batch 2 Final SME Product for Redox Adjustment 1
E 1.99:wsrc-tr-2002-00059 Savannah River Site Waste Removal Program - Past, Present and Future 1
E 1.99:wsrc-tr-2002-00060 Solvent Composition Impacts on the Extraction of Uranium and Plutonium in the Caustic Side Solvent Extraction Process 1
E 1.99:wsrc-tr-2002-00062 RPP-WTP Slurry Wear Evaluation Slurry Abrasivity. 1
E 1.99:wsrc-tr-2002-00065 Vapor Corrosion Program Plan 1
E 1.99:wsrc-tr-2002-00070 Yield Stress and Physical Data Results for the Tank 19F Radioactive Mound Sample and Tank 19F Simulant Samples 1
E 1.99:wsrc-tr-2002-00071 Assessment of Tank 18 Corrosion During Waste Removal 1
E 1.99:wsrc-tr-2002-00076 Confirmation Run of the DWPF SRAT Cycle Using the Sludge-Only Flowsheet with Tank 40 Radioactive Sludge and Frit 200 in the Shielded Cells Facility 1
E 1.99:wsrc-tr-2002-00077 55-Gallon Drum Attenuation Corrections for Waste Assay Measurements 1
E 1.99:wsrc-tr-2002-00078 Mechanism of Pitting Corrosion Prevention by Nitrite in Carbon Steel Exposed to Dilute Salt Solutions 1
E 1.99:wsrc-tr-2002-00080 D-Area Drip Irrigation-Phytoremediation Project SRTC Final Report. 1
E 1.99:wsrc-tr-2002-00090 Pretreatment of PUREX Waste Solvent by Ion Exchange and Solvent Extraction 1
E 1.99:wsrc-tr-2002-00091 Resin Longevity Studies 1
E 1.99:wsrc-tr-2002-00093 Large Scale Vitrification of 241-AN-102 (Envelope C) Sample 1
E 1.99:wsrc-tr-2002-00096 Confirmation Run of the DWPF SRAT Cycle Results of the Glass Analysis Using the Sludge-Only Flowsheet with Tank 40 Radioactive Sludge and Frit 200 in the Shielded Cells Facility 1