MARITIME REACTOR WASTE DISPOSAL STUDIES: SOLIDIFICATION OF ION-EXCHANGE RESIN WITH PORTLAND CEMENT FOR RADIOACTIVE DISPOSAL

A procedure is reported for the sea disposal, by fixation in concrete with Portland cement, of ion-exchange resins containing sorbed fission products and filtered corrosion products. The results of sea disposal of both treated and untreated resins is presented. For the fixation of nuclear reactor-system demineralizer resin in cement, a mixture of 2 parts of cement, 1 part of resin, and 1 part of water was found to be optimum. A concrete block prepared by this receipt showed only 0.44% of the gross gamma activity leached after 2540 hr of contact with simulated sea water. The data indicate that very little or no further leaching will occur. (Author)

  • Supplemental Notes:
    • This document is available for review at the Department of Commerce Library, Main Commerce Building, Washington, D.C., under reference number ORNL-2899.
  • Corporate Authors:

    Oak Ridge National Laboratory

    Chemical Technology Division
    Oak Ridge, TN  USA 

    UNION CARBIDE CORPORATION

    OAK RIDGE, TN  USA 
  • Authors:
    • Holcomb, R R
  • Publication Date: 1960-9-13

Media Info

  • Features: Figures; Photos; References; Tables;
  • Pagination: 16 p.

Subject/Index Terms

Filing Info

  • Accession Number: 00026315
  • Record Type: Publication
  • Source Agency: Maritime Administration
  • Report/Paper Numbers: ORNL-2899
  • Contract Numbers: W-7405-eng26
  • Files: TRIS, USDOT
  • Created Date: May 11 1973 12:00AM