Download or read book REMOVAL OF TECHNETIUM 99 FROM THE EFFLUENT TREATMENT FACILITY ETF BASIN 44 USING PUROLITE A 530E REILLEX HPQ SYBRON IONAC SR 7 ION EXCHANGE RESINS written by DUNCAN JB. and published by . This book was released on 2004 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report documents the laboratory testing and analyses as directed under the test plan, RPP-20407. The overall goal of this task was to evaluate and compare candidate anion exchange resins for their capacity to remove Technetium-99 from Basin 44 Reverse Osmosis reject stream. The candidate resins evaluated were Purolite A-530E, Reillex HPQ, and Sybron IONAC SR-7.

Download or read book LABORATORY REPORT ON THE REMOVAL OF PERTECHNETATE FROM TANK 241 AN 105 SIMULANT USING PUROLITE A530E written by and published by . This book was released on 2012 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This report documents the laboratory testing and analyses as directed under the test plan, LAB-PLN-11-00010, Evaluation of Technetium Ion Exchange Material against Hanford Double Shell Tank Supernate Simulate with Pertechnetate. Technetium (Tc-99) is a major fission product from nuclear reactors, and because it has few applications outside of scientific research, most of the technetium will ultimately be disposed of as nuclear waste. The radioactive decay of Tc-99 to ruthenium 99 (Ru-99) produces a low energy?− particle (0.1 MeV max). However, due to its fairly long half-life (t12 = 2.13E05 years), Tc-99 is a major source of radiation in low-level waste (UCRL-JRNL-212334, Current Status of the Thermodynamic Data for Technetium and its Compounds and Aqueous Species). Technetium forms the soluble oxy anion, TcO4− under aerobic conditions. This anion is very mobile in groundwater and poses a health risk (ANL, Radiological and Chemical Fact Sheets to Support Health Risk Analyses for Contaminated Areas). It has been demonstrated that Purolite{reg_sign} A530E is highly effective in removing TcO4− from a water matrix (RPP-RPT-23199, The Removal of Technetium-99 from the Effluent Treatment Facility Basin 44 Waste Using Purolite A-530E, Reillex HPQ, and Sybron IONAC SR-7 Ion Exchange Resins). Purolite{reg_sign} A530E is the commercial product of the Oak Ridge National Laboratory's Biquat{trademark} resin (Gu, B. et. ai, Development of Novel Bifunctional Anion-Exchange Resins with Improved Selectivity for Pertechnetate Sorption from Contaminated Groundwater). Further work has demonstrated that technetium-loaded A530E achieves a leachability index in Cast Stone of 12.5 (ANSI/ASN-16.1-2003, Measurement of the Leachability of Solidified Low-Level Radioactive Wastes by a Short-term Test Procedure) as reported in RPP-RPT-39195, Assessment of Technetium Leachability in Cement-Stabilized Basin 43 Groundwater Brine. This effort falls under the technetium management initiative and will provide data for those who will make decisions on the handling and disposition of technetium. To that end, the objective of this effort was to challenge Purolite{reg_sign} A530E against a double-shell tank (DST) simulant (tank 241-AN-105 or AN-105) spiked with pertechnetate (TcO4−) to determine breakthrough of the lead column.

Download or read book Treatability Test for Removing Technetium 99 from 200 ZP 1 Groundwater Hanford Site written by and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: The 200-ZP-1 Groundwater Operable Unit (OU) is one of two groundwater OUs located within the 200 West groundwater aggregate area of the Hanford Site. The primary risk-driving contaminants within the 200-ZP-1 OU include carbon tetrachloride and technetium-99 (Tc-99). A pump-and-treat system for this OU was initially installed in 1995 to control the 0.002 kg/m3 (2000 [mu]g/L) contour of the carbon tetrachloride plume. Carbon tetrachloride is removed from groundwater with the assistance of an air-stripping tower. Ten extraction wells and three injection wells operate at a combined rate of approximately 0.017m3/s (17.03 L/s). In 2005, groundwater from two of the extraction wells (299-W15-765 and 299-W15-44) began to show concentrations greater than twice the maximum contaminant level (MCL) of Tc-99 (33,309 beq/m3 or 900 pCi/L). The Tc-99 groundwater concentrations from all ten of the extraction wells when mixed were more than one-half of the MCL and were slowly increasing. If concentrations continued to rise and the water remained untreated for Tc-99, there was concern that the water re-injected into the aquifer could exceed the MCL standard. Multiple treatment technologies were reviewed for selectively removing Tc-99 from the groundwater. Of the treatment technologies, only ion exchange was determined to be highly selective, commercially available, and relatively low in cost. Through research funded by the U.S. Department of Energy, the ion-exchange resin Purolite{reg_sign} A-530E was found to successfully remove Tc-99 from groundwater, even in the presence of competing anions. For this and other reasons, Purolite{reg_sign} A-530E ion exchange resin was selected for treatability testing. The treatability test required installing resin columns on the discharge lines from extraction wells 299-W15-765 and 299-W15-44. Preliminary test results have concluded that the Purolite{reg_sign} A-530E resin is effective at removing Tc-99 from groundwater to below detection limits even in the presence of competing anions (e.g., nitrate and sulfate) at concentrations five to six magnitudes higher than Tc-99.

Download or read book An Evaluation of an Ion exchange Method for the Removal of Technetium 99 from Groundwater written by Wanda Sue Elliott and published by . This book was released on 2007 with total page 34 pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Removal of Technetium 99 from Simulated Oak Ridge National Laboratory Newly Generated Liquid Low Level Waste written by and published by . This book was released on 1995 with total page 24 pages. Available in PDF, EPUB and Kindle. Book excerpt: We report laboratory investigations on treatment options for the removal of the radionuclide 99{Tc} (as the pertechnetate anion, {Tc}O4−) from simulated Oak Ridge National Laboratory Newly Generated Liquid Low-Level Waste. The waste stimulant is alkaline (pH 12-13), containing sodium carbonate ((approximately)0.10 mot/L) and sodium hydroxide ((approximately) 0.125 mol/L), plus a modest concentration of sodium nitrate ((approximately)0.06 mol/L). Several organic resin anion exchange media were tested; Dowex{trademark} 1-X-8 and Reillex{trademark} HPQ resins were notably effective (with equilibrium distribution coefficients (approximately)2,000 mL/g, as-received basis). We also tested steel wool as a reagent to chemically reduce and sorb 99Tc. At pH values above (approximately)10, the iron surface was passivated and became ineffective as a reagent for technetium; however, as the test solution pH value was adjusted to near-neutrality (e.g., pH 8-9), the steel was noted to be more effective than the organic resins tested. In dynamic flow conditions, steel wool packed in a column was noted to continuously leak (approximately)1--3% of the amount of 99{Tc} activity in the feed solution, although no additional increase in eluent activity was noted for the duration of the testing ((approximately)1200 bed volumes of (approximately)0.11 mg/L 99{Tc} flowed at a rate equivalent to (approximately)0.5 gal/min/ft2 of column cross sectional area). Although no breakthrough was noted (other than the 1--3 % continuous ''bleed'' noted previously) during the column operation ((approximately) 2 weeks), the steel in the column was deteriorated, causing plugging and erratic flow toward the end of the testing interval.

Download or read book Treatability Test Plan for Using Purolite Resin to Remove Technetium 99 from 200 ZP 1 Groundwater written by United States. Department of Energy. Richland Operations Office and published by . This book was released on 2007 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt:

Download or read book Technology Transfer written by and published by . This book was released on 1982 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: An ion exchange process will be used at Portsmouth to remove Technetium-99 from uranium recovery waste solutions (raffinates). Subsequent treatment will then remove nitrates from the raffinates by a biodenitrification process prior to discharge to receiving streams to meet environmental standards for liquid wastes. Ion exchange process parameters affecting safe and efficient raffinate treatment have been examined in the laboratory, and results are described in this report. 4 refs., 3 figs., 6 tabs.

Download or read book Intermediate Scale Ion Exchange Removal of Technetium from Savannah River Site Tank 44 F Supernate Solution written by and published by . This book was released on 2000 with total page 5 pages. Available in PDF, EPUB and Kindle. Book excerpt: As part of the Hanford River Protection Project waste Treatment facility design contracted to BNFL, Inc., a sample of Savannah River Site (SRS) Tank 4 F waste solution was treated for the removal of technetium (as pertechnetate ion). Interest in treating the SRS sample for Tc removal resulted from the similarity between the Tank 44 F supernate composition and Hanford Envelope A supernate solutions. The Tank 44 F sample was available as a by-product of tests already conducted at the Savannah River Technology Center (SRTC) as part of the Alternative Salt Disposition Program for treatment of SRS wastes. Testing of the SRS sample resulted in considerable cost-savings since it was not necessary to ship a sample of Hanford supernate to SRS.