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Title: Removal of technetium-99 from simulated Oak Ridge National Laboratory Newly-Generated Liquid Low-Level Waste

Abstract

We report laboratory investigations on treatment options for the removal of the radionuclide {sup 99}{Tc} (as the pertechnetate anion, {Tc}O{sub 4}{sup {minus}}) 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 {sup 99}Tc. 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 {sup 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 {sup 99}{Tc} flowed at a rate equivalentmore » to {approximately}0.5 gal/min/ft{sup 2} 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.« less

Authors:
; ; ; ; ; ;  [1];  [2]
  1. Oak Ridge K-25 Site, TN (United States)
  2. Oak Ridge National Lab., TN (United States)
Publication Date:
Research Org.:
Oak Ridge K-25 Site, TN (United States)
Sponsoring Org.:
USDOE, Washington, DC (United States)
OSTI Identifier:
95161
Report Number(s):
K/TCD-1141
ON: DE95014419; TRN: 95:018499
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: Jun 1995
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; 40 CHEMISTRY; LOW-LEVEL RADIOACTIVE WASTES; RADIOCHEMICAL ANALYSIS; ORNL; RADIOACTIVE WASTE STORAGE; TECHNETIUM 99; TANKS; STRONTIUM 90; RUTHENIUM 106; CESIUM 137; NITRATES

Citation Formats

Beck, D E, Osborne, P E, Bunch, D H, Fellows, R L, Sellers, G F, Shoemaker, J L, Bowser, K T, and Bostick, D T. Removal of technetium-99 from simulated Oak Ridge National Laboratory Newly-Generated Liquid Low-Level Waste. United States: N. p., 1995. Web. doi:10.2172/95161.
Beck, D E, Osborne, P E, Bunch, D H, Fellows, R L, Sellers, G F, Shoemaker, J L, Bowser, K T, & Bostick, D T. Removal of technetium-99 from simulated Oak Ridge National Laboratory Newly-Generated Liquid Low-Level Waste. United States. https://doi.org/10.2172/95161
Beck, D E, Osborne, P E, Bunch, D H, Fellows, R L, Sellers, G F, Shoemaker, J L, Bowser, K T, and Bostick, D T. Thu . "Removal of technetium-99 from simulated Oak Ridge National Laboratory Newly-Generated Liquid Low-Level Waste". United States. https://doi.org/10.2172/95161. https://www.osti.gov/servlets/purl/95161.
@article{osti_95161,
title = {Removal of technetium-99 from simulated Oak Ridge National Laboratory Newly-Generated Liquid Low-Level Waste},
author = {Beck, D E and Osborne, P E and Bunch, D H and Fellows, R L and Sellers, G F and Shoemaker, J L and Bowser, K T and Bostick, D T},
abstractNote = {We report laboratory investigations on treatment options for the removal of the radionuclide {sup 99}{Tc} (as the pertechnetate anion, {Tc}O{sub 4}{sup {minus}}) 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 {sup 99}Tc. 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 {sup 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 {sup 99}{Tc} flowed at a rate equivalent to {approximately}0.5 gal/min/ft{sup 2} 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.},
doi = {10.2172/95161},
url = {https://www.osti.gov/biblio/95161}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1995},
month = {6}
}