Properties of radioactive wastes and waste containers. Quarterly progress report, April--June 1976

Technical Report · Thu Jan 01 04:00:00 EST 1976

OSTI ID:7214154

Colombo, P; Neilson, Jr, R M

This program will initiate an independent study to measure waste form and package properties relevant to isolating radionuclides from the environment and allow an assessment of the adequacy of current and proposed radioactive waste packages. The initial phase will concern itself with solidified liquid concentrate and solid wastes generated as by-products of the liquid radwaste treatment systems in boiling water reactors (BWR) and pressurized water reactors (PWR). The objectives and tentative schedule for this program are reviewed. Experimental formulations for the solidification of specified waste types with portland cement and urea-formaldehyde are described. These formulations are based on information obtained from radioactive waste solidification services and laboratory trials and will be used in the production of specimens for testing purposes. A proposed static leach testing procedure is reviewed. The effect of the sampling interval on the release of strontium from portland type II cement was determined. These results indicate that a sampling frequency of once per day provides reproducible results. Hydrostatic testing of DOT 17C and DOT 17H carbon steel 55 gallon drums was performed. Removable head drums exhibited leakage at the gasket at an average pressure of 16 psi and 1.3 psi for DOT 17C and DOT 17H drums, respectively. Closed head drums sustained higher pressures. Closed head drum leakage occurred along the top head seam which unrolled as the drum head deformed under increasing hydrostatic pressure. The weight loss upon exposure to ambient air and unnotched Izod impact strength as a function of weight loss for urea-formaldehyde specimens were determined.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: EY-76-C-02-0016
• OSTI ID: 7214154
• Report Number(s): BNL-NUREG-50571
• Country of Publication: United States
• Language: English

Related Subjects

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12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALDEHYDES
ALKALINE EARTH METALS
AMIDES
BUILDING MATERIALS
BWR TYPE REACTORS
CARBONIC ACID DERIVATIVES
CEMENTS
CONTAINERS
DISSOLUTION
ELEMENTS
FORMALDEHYDE
LEACHING
LIQUID WASTES
MANAGEMENT
MATERIALS
METALS
ORGANIC COMPOUNDS
ORGANIC NITROGEN COMPOUNDS
PACKAGING
PERFORMANCE
PHASE TRANSFORMATIONS
PORTLAND CEMENT
PROCESSING
PWR TYPE REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTE PROCESSING
RADIOACTIVE WASTES
REACTORS
SEPARATION PROCESSES
SOLID WASTES
SOLIDIFICATION
STRONTIUM
TANKS
TESTING
UREA
WASTE MANAGEMENT
WASTE PROCESSING
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS