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 ar...