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  United States 

  UNION CARBIDE CORPORATION

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

Media Info

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

Subject/Index Terms

• TRT Terms: Radioactive wastes; Resins; Spent reactor fuels
• Subject Areas: Environment; Marine Transportation;

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