Properties of radioactive wastes and waste containers. Progress report No. 10, July-September 1978

Technical Report · Tue May 01 04:00:00 EDT 1979

DOI:https://doi.org/10.2172/5951368· OSTI ID:5951368

Colombo, P; Neilson, Jr, R M

Modified IAEA and equilibrium leaching studies were performed using portland cement, urea-formaldehyde and vinyl ester-styrene waste forms containing BWR chemical regenerative waste. This set of experiments, with its range of leachant replacement intervals, should cover the range of expected leach rates for most conditions. The equilibrium leach method generally resulted in lower release rates than the modified IAEA method. In the case of strontium-85 release from portland cement, this decrease was dramatic. The use of finite and semi-infinite diffusional mass transport models for leaching data analysis to predict long-term releases from full scale waste forms is discussed. While the finite model can give a more accurate description of activity release since it considers specimen depletion effects, the double series function solution converges slowly for small effective diffusivities and small total numbers of summation terms. This can result in computer truncation error dominating in the solutions for small releases. In this report period, the first topical report for the program Properties of Radioactive Wastes and Waste Containers was also written. This document appears under a separate cover.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: EY-76-C-02-0016
• OSTI ID: 5951368
• Report Number(s): NUREG/CR-0857; BNL-NUREG-51026
• Country of Publication: United States
• Language: English

Related Subjects

052002* -- Nuclear Fuels-- Waste Disposal & Storage
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
ALDEHYDES
ALKALI METAL ISOTOPES
ALKALINE EARTH ISOTOPES
AMIDES
AROMATICS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
BWR TYPE REACTORS
CARBONIC ACID DERIVATIVES
CEMENTS
CESIUM 137
CESIUM ISOTOPES
COBALT 60
COBALT ISOTOPES
CONTAINERS
DAYS LIVING RADIOISOTOPES
DISSOLUTION
ELECTRON CAPTURE RADIOISOTOPES
EVEN-ODD NUCLEI
FORMALDEHYDE
HOURS LIVING RADIOISOTOPES
HYDROCARBONS
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
LEACHING
MATERIALS
MINUTES LIVING RADIOISOTOPES
MONOMERS
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
ORGANIC COMPOUNDS
ORGANIC NITROGEN COMPOUNDS
ORGANIC POLYMERS
PETROCHEMICALS
PETROLEUM PRODUCTS
POLYMERS
PORTLAND CEMENT
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
RADIOISOTOPES
REACTORS
RESEARCH PROGRAMS
RESINS
SEPARATION PROCESSES
SOLID WASTES
STRONTIUM 85
STRONTIUM ISOTOPES
STYRENE
UREA
VINYL MONOMERS
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
YEARS LIVING RADIOISOTOPES