In-tank processes for destruction of organic complexants and removal of selected radionuclides Metadata

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Title

  • Main Title In-tank processes for destruction of organic complexants and removal of selected radionuclides

Creator

  • Author: Schulz, W. W.
    Creator Type: Personal
  • Author: Kupfer, M. J.
    Creator Type: Personal
  • Author: McKeon, M. M.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: USDOE, Washington, DC (United States)

Publisher

  • Name: Westinghouse Hanford Company
    Place of Publication: Richland, Washington
    Additional Info: Westinghouse Hanford Co., Richland, WA (United States)

Date

  • Creation: 1995-02-01

Language

  • English

Description

  • Content Description: This report establishes the need and technical feasibility for using in-tank pretreatment processes for destruction of organic complexants and removal of {sup 90}Sr, transuranic (TRU) elements, and {sup 99}Tc from double-shell tank (DST) liquid wastes. Neither {sup 90}Sr nor {sup 99}{Tc} have to be removed from any DST solution to obtain vitrified product containing less than the Nuclear Regulatory Commission (NRC) criteria for Class C commercial low-level waste (LLW). To meet the NRC criterion for Class C LLW, TRU elements must be removed from liquid wastes in three (possibly five) DSTs. No {sup 90}Sr will have to be removed from any solution for the total vitrified waste from both DSTs and single-shell tanks to meet a goal of <7 MCi of radionuclides and a NRC ruling for Hanford Site Incidental Waste. Guidance from ALARA principles and the TWRS Environmental Impact Statement may dictate additional removal of radionuclides from DST supernatant liquids. Scavenging processes involving precipitation of strontium phosphate and/or hydrated iron oxide effectively remove {sup 90}Sr and/or TRU elements from actual DST wastes including complexant concentrate (CC) wastes. Destruction of organic complexants is not required for these scavenging processes to reduce the {sup 90}Sr and/or TRU element concentrations of DST waste solutions to or below the NRC criteria for Class C commercial LLW. However, substantially smaller amounts of scavenging agents would be required for removal of {sup 90}Sr and TRU elements from CC waste if organic complexants were destroyed. Low concentrations of added Sr(NO{sub 3}){sub 2} and Fe(NO{sub 3}){sub 3} are desirable to minimize the volume of HLW glass.
  • Physical Description: 62 p.

Subject

  • Keyword: Technetium 99
  • Keyword: Radioactive Waste Processing
  • Keyword: Radioactive Waste Storage
  • Keyword: Technetium Compounds
  • Keyword: Recommendations
  • Keyword: Specifications
  • Keyword: Strontium Nitrates
  • Keyword: Radioactive Wastes
  • STI Subject Categories: 05 Nuclear Fuels
  • Keyword: Organic Compounds
  • Keyword: Alpha-Bearing Wastes
  • Keyword: Tanks
  • Keyword: Cesium 137
  • Keyword: Sorption
  • Keyword: Us Nrc
  • Keyword: Ozone
  • Keyword: Precipitation
  • Keyword: Strontium 90

Source

  • Other Information: PBD: Feb 1995

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report

Format

  • Text

Identifier

  • Other: DE95011673
  • Report No.: WHC-SD-WM-ES--321
  • Grant Number: AC06-87RL10930
  • DOI: 10.2172/61716
  • Office of Scientific & Technical Information Report Number: 61716
  • Archival Resource Key: ark:/67531/metadc696418

Note

  • Display Note: INIS; OSTI as DE95011673
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