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

R. R. Holcomb | Zendy

Open Access

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

Author(s) -

R. R. Holcomb

Publication year - 1960

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/4148981

Subject(s) - radioactive waste , leaching (pedology) , waste management , cement , portland cement , environmental science , ion exchange resin , leachate , fission products , ion exchange , nuclear chemistry , materials science , radiochemistry , metallurgy , chemistry , ion , engineering , inorganic chemistry , organic chemistry , soil science , soil water

A procedure is reported for the sea disposal. by fixation in concrete. 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. (auth

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