Tank 241-AZ-102 SuperLig 639 Technetium Ion Exchange Eluate Evaporation Study

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Description

As part of the Hanford River Protection Project (RPP), the Savannah River Technology Center (SRTC) has conducted tests on the pretreatment and vitrification of a radioactive waste sample from Hanford Tank 241-AZ-102. The original, AZ-102 sample which was received at SRTC was characterized and filtered to remove entrained solids.1 The sample was then passed sequentially through ion exchange columns containing SuperLig{reg_sign} 644 and 639 resins for the removal of cesium and technetium ions (Tc removed as pertechnetate, TcO{sub 4}{sup {minus}}), respectively.2 The cesium and technetium absorbed to the resins was then eluted to give separate eluate solutions containing relatively high ... continued below

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24 pages

Creation Information

King, W. D. February 15, 2001.

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This report is part of the collection entitled: Office of Scientific & Technical Information Technical Reports and was provided by UNT Libraries Government Documents Department to Digital Library, a digital repository hosted by the UNT Libraries. It has been viewed 19 times , with 4 in the last month . More information about this report can be viewed below.

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Description

As part of the Hanford River Protection Project (RPP), the Savannah River Technology Center (SRTC) has conducted tests on the pretreatment and vitrification of a radioactive waste sample from Hanford Tank 241-AZ-102. The original, AZ-102 sample which was received at SRTC was characterized and filtered to remove entrained solids.1 The sample was then passed sequentially through ion exchange columns containing SuperLig{reg_sign} 644 and 639 resins for the removal of cesium and technetium ions (Tc removed as pertechnetate, TcO{sub 4}{sup {minus}}), respectively.2 The cesium and technetium absorbed to the resins was then eluted to give separate eluate solutions containing relatively high concentrations of Cs{sup +} and TcO{sub 4}{sup {minus}}. According to the current plant design, the decontaminated Tank 241-AZ-102 sample and the eluate solutions will be subjected to separate evaporation and vitrification processes to give low- and high-activity waste glasses, respectively. This report describes evaporation testing of the Tc eluate solution derived from ion exchange processing of the Tank 241-AZ-102 sample with SuperLig 639 resin.

Physical Description

24 pages

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  • Other Information: PBD: 15 Feb 2001

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  • Report No.: WSRC-TR-2000-00424 SRT-RPP-2000-00024 Rev. 0
  • Grant Number: AC09-96SR18500
  • DOI: 10.2172/774861 | External Link
  • Office of Scientific & Technical Information Report Number: 774861
  • Archival Resource Key: ark:/67531/metadc717359

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Creation Date

  • February 15, 2001

Added to The UNT Digital Library

  • Sept. 29, 2015, 5:31 a.m.

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  • May 5, 2016, 5:34 p.m.

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King, W. D. Tank 241-AZ-102 SuperLig 639 Technetium Ion Exchange Eluate Evaporation Study, report, February 15, 2001; South Carolina. (digital.library.unt.edu/ark:/67531/metadc717359/: accessed September 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.