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 |