Properties of radioactive wastes and waste containers. Progress report No. 5, April--June 1977

Technical Report · Tue Nov 01 04:00:00 EST 1977

DOI:https://doi.org/10.2172/6708861· OSTI ID:6708861

Colombo, P; Neilson, Jr, R M

Portland type II cement decontamination factors for free standing water were determined to be 1, 11, and 200 for /sup 137/Cs, /sup 85/Sr, and /sup 60/Co respectively, indicating ion exchange processes occurring within the cement matrix. The quantity of organic carbon that could be removed from solidification agent matrix materials on leaching in distilled water was measured. No organic carbon was present in the portland type II cement leachant water after ten days while 3.4 ppM, 34.2 ppM, and 9500 ppM organic carbon were present respectively in the bitumen, Dow polymer and urea-formaldehyde leachant water (300 ml). The compression strengths of portland type II cement and urea-formaldehyde waste forms containing various simulated wastes were measured. The effect of the waste/cement ratio on the compression strength of portland type II cement simulated waste forms was also studied. The gamma radiation shielding characteristics of portland cement, urea-formaldehyde, and bitumen waste forms were studied in reference to the maximum incorporated activity permissible in 55 gallon waste packages for transportation in ''non-exclusive use'' vehicles under 49CFR173. Thermal conductivity, specific heat, and thermal diffusivity values were obtained for portland cement, urea-formaldehyde, bitumen, and Dow polymer waste forms. Solidification verification studies were initiated for the Dow polymer at waste/binder ratios representative of those proposed for use by the vendor. Successful solidifications were obtained for all waste types tested with the exception of 12 wt.% boric acid. The 12 wt.% boric acid waste was successfully solidified after a proprietary pretreatment of the waste stream.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: EY-76-C-02-0016
• OSTI ID: 6708861
• Report Number(s): BNL-NUREG-50763
• Country of Publication: United States
• Language: English

Related Subjects

052000* -- Nuclear Fuels-- Waste Management
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALDEHYDES
AMIDES
BIODEGRADATION
BITUMENS
BORIC ACID
BUILDING MATERIALS
CARBONIC ACID DERIVATIVES
CEMENTS
CHEMICAL REACTIONS
CLEANING
COMPRESSION STRENGTH
DECOMPOSITION
DECONTAMINATION
DISSOLUTION
ELECTROMAGNETIC RADIATION
FORMALDEHYDE
GAMMA RADIATION
HYDROGEN COMPOUNDS
INORGANIC ACIDS
IONIZING RADIATIONS
LEACHING
MANAGEMENT
MATERIALS
MATRIX MATERIALS
MECHANICAL PROPERTIES
ORGANIC COMPOUNDS
ORGANIC NITROGEN COMPOUNDS
OTHER ORGANIC COMPOUNDS
PHASE TRANSFORMATIONS
PHYSICAL PROPERTIES
POLYMERS
PORTLAND CEMENT
PROCESSING
RADIATIONS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
RADIOACTIVITY
REACTOR MATERIALS
RESEARCH PROGRAMS
SEPARATION PROCESSES
SHIELDING
SOLID WASTES
SOLIDIFICATION
SPECIFIC HEAT
TAR
THERMAL CONDUCTIVITY
THERMODYNAMIC PROPERTIES
UREA
WASTE MANAGEMENT
WASTE PROCESSING
WASTES