Properties of radioactive wastes and waste containers. Quarterly progress report, January--March 1977

• Main Authors: Colombo, P., Neilson, R.M. Jr.
• Language: unknown
• Published: 2012
• Subjects: 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; CESIUM 137; LEACHING; CONTAINERS; PERFORMANCE TESTING; RADIOACTIVE WASTE PROCESSING; SOLIDIFICATION; RADIOACTIVE WASTES; DENSITY; STRONTIUM 85; CEMENTS; FORMALDEHYDE; RESEARCH PROGRAMS; UREA; ALDEHYDES; ALKALI METAL ISOTOPES; ALKALINE EARTH ISOTOPES; AMIDES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; BUILDING MATERIALS; CARBONIC ACID DERIVATIVES; CESIUM ISOTOPES; DAYS LIVING RADIOISOTOPES; DISSOLUTION; ELECTRON CAPTURE RADIOISOTOPES; EVEN-ODD NUCLEI; HOURS LIVING RADIOISOTOPES; INTERMEDIATE MASS NUCLEI; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MANAGEMENT; MATERIALS; NUCLEI; ODD-EVEN NUCLEI; ORGANIC COMPOUNDS; ORGANIC NITROGEN COMPOUNDS; PHASE TRANSFORMATIONS; PHYSICAL PROPERTIES; PROCESSING; RADIOACTIVE MATERIALS; RADIOISOTOPES; SEPARATION PROCESSES; STRONTIUM ISOTOPES; TESTING; WASTE MANAGEMENT; WASTE PROCESSING; WASTES; YEARS LIVING RADIOISOTOPES; Open Head; Carbonic acid
• Online Access: http://www.osti.gov/servlets/purl/6567177; https://www.osti.gov/biblio/6567177; https://doi.org/10.2172/6567177

The densities of the simulated wastes used in this program were determined and factors reported to allow conversion of formulation data for urea-formaldehyde (UF) waste forms from weight ratios to volume ratios of waste to UF. Simulated Solka-Floc wastes were solidified with urea-formaldehyde but areas of unsolidified Solka-Floc were found in the final waste forms. The difficulty in mixing dewatered Solka-Floc waste with UF is presumed to be responsible. Attempts to solidify alkaline regenerative wastes with urea-formaldehyde were not successful. Increasing the waste/UF volume ratio to 3.0 produced acceptable solids with boric acid and decontamination waste, but not with chemical regenerative wastes. The use of masonry cement (one part Portland cement to one part anhydrous lime by weight) for the solidification of boric acid concentrate waste was investigated. Free standing solids were formed at waste/cement weight ratios of 0.6 and 1.0 but not at 1.5 or 2.0. Masonry cement was found to be superior to Portland cement for the solidification of boric acid wastes. The weight loss with temperature of urea-formaldehyde waste forms containing various simulated wastes was measured over the range of 25 to 500/sup 0/C. Weight losses due to the evaporation of water, decomposition of UF and decomposition of the wastes were observed. Static leaching experiments were conducted to determine the rate of release of cesium-137 and strontium-85 from urea-formaldehyde specimens and bead and powdered cation exchange resins. Results for the leaching of these materials in salt water, tap water, and distilled water are reported. Hydrostatic testing of modified DOT 17H open head 55 gallon drums was performed. These drums met the required DOT specifications and ultimately failed at an average pressure of 44 psig by separation of the drum head from the drum body at the gasket.