Properties of radioactive wastes and waste containers. Quarterly progress report, October--December 1976. [Urea-formaldehyde; polymer; portland cement]

The cumulative quantities of free standing water resulting from the solidification of simulated wastes with urea-formaldehyde (UF) and portland type II cement were determined. The effect of the waste/solidification agent ratio on the cumulative free standing water for selected wastes solidified with...

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Main Authors: Colombo, P., Neilson, R.M. Jr.
Language:unknown
Published: 2012
Subjects:
Online Access:http://www.osti.gov/servlets/purl/7309235
https://www.osti.gov/biblio/7309235
https://doi.org/10.2172/7309235
id ftosti:oai:osti.gov:7309235
record_format openpolar
spelling ftosti:oai:osti.gov:7309235 2023-07-30T04:02:56+02:00 Properties of radioactive wastes and waste containers. Quarterly progress report, October--December 1976. [Urea-formaldehyde; polymer; portland cement] Colombo, P. Neilson, R.M. Jr. 2012-12-12 application/pdf http://www.osti.gov/servlets/purl/7309235 https://www.osti.gov/biblio/7309235 https://doi.org/10.2172/7309235 unknown http://www.osti.gov/servlets/purl/7309235 https://www.osti.gov/biblio/7309235 https://doi.org/10.2172/7309235 doi:10.2172/7309235 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES RADIOACTIVE WASTE PROCESSING SOLIDIFICATION CESIUM 137 COBALT 60 COMPRESSION STRENGTH DECONTAMINATION EFFICIENCY FORMALDEHYDE IMPACT STRENGTH IRON 59 LEACHING POLYMERS PORTLAND CEMENT STABILITY STRONTIUM 85 THERMAL CONDUCTIVITY UREA WASTE WATER ALDEHYDES ALKALI METAL ISOTOPES ALKALINE EARTH ISOTOPES AMIDES BETA DECAY RADIOISOTOPES BETA-MINUS DECAY RADIOISOTOPES BUILDING MATERIALS CARBONIC ACID DERIVATIVES CEMENTS CESIUM ISOTOPES CLEANING COBALT ISOTOPES DAYS LIVING RADIOISOTOPES DISSOLUTION ELECTRON CAPTURE RADIOISOTOPES EVEN-ODD NUCLEI HOURS LIVING RADIOISOTOPES HYDROGEN COMPOUNDS INTERMEDIATE MASS NUCLEI INTERNAL CONVERSION RADIOISOTOPES IRON ISOTOPES ISOMERIC TRANSITION ISOTOPES ISOTOPES LIQUID WASTES MANAGEMENT MATERIALS MECHANICAL PROPERTIES MINUTES LIVING RADIOISOTOPES NUCLEI ODD-EVEN NUCLEI ODD-ODD NUCLEI 2012 ftosti https://doi.org/10.2172/7309235 2023-07-11T10:55:54Z The cumulative quantities of free standing water resulting from the solidification of simulated wastes with urea-formaldehyde (UF) and portland type II cement were determined. The effect of the waste/solidification agent ratio on the cumulative free standing water for selected wastes solidified with UF was found to be related to sample shrinkage. Urea-formaldehyde decontamination factors for free standing water were determined with /sup 137/Cs, /sup 85/Sr, /sup 60/Co, and /sup 59/Fe. With the exception of /sup 85/Sr for which UF was shown to have a decontamination factor of 1.6-1.9, the specific activity of the free standing water was essentially equal to that of the waste prior to solidification. The release of cesium from UF in distilled water was measured by a static leaching technique. The effect of the leachant renewal interval and the ratio of the leachant volume (V/sub L/) to the sample external geometric surface area (S) was examined. The proposed leachant renewal interval of once/day and V/sub L/S = 10cm was found to be satisfactory for leaching of these samples. Samples of a proprietary polymer agent developed by the Dow Chemical Company were tested to determine water loss with exposure to ambient air, weight loss with temperature (TGA), thermal conductivity, compressive strength and impact strength. Property measurements were made for water/binder volume ratios of from 1.0 to 2.0. No deterioration was observed for a portland type II cement sample with a water/cement ratio of 0.5 by weight subjected to fifty freeze-thaw cycles. Other/Unknown Material Carbonic acid SciTec Connect (Office of Scientific and Technical Information - OSTI, U.S. Department of Energy)
institution Open Polar
collection SciTec Connect (Office of Scientific and Technical Information - OSTI, U.S. Department of Energy)
op_collection_id ftosti
language unknown
topic 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
RADIOACTIVE WASTE PROCESSING
SOLIDIFICATION
CESIUM 137
COBALT 60
COMPRESSION STRENGTH
DECONTAMINATION
EFFICIENCY
FORMALDEHYDE
IMPACT STRENGTH
IRON 59
LEACHING
POLYMERS
PORTLAND CEMENT
STABILITY
STRONTIUM 85
THERMAL CONDUCTIVITY
UREA
WASTE WATER
ALDEHYDES
ALKALI METAL ISOTOPES
ALKALINE EARTH ISOTOPES
AMIDES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CARBONIC ACID DERIVATIVES
CEMENTS
CESIUM ISOTOPES
CLEANING
COBALT ISOTOPES
DAYS LIVING RADIOISOTOPES
DISSOLUTION
ELECTRON CAPTURE RADIOISOTOPES
EVEN-ODD NUCLEI
HOURS LIVING RADIOISOTOPES
HYDROGEN COMPOUNDS
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
IRON ISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
LIQUID WASTES
MANAGEMENT
MATERIALS
MECHANICAL PROPERTIES
MINUTES LIVING RADIOISOTOPES
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
spellingShingle 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
RADIOACTIVE WASTE PROCESSING
SOLIDIFICATION
CESIUM 137
COBALT 60
COMPRESSION STRENGTH
DECONTAMINATION
EFFICIENCY
FORMALDEHYDE
IMPACT STRENGTH
IRON 59
LEACHING
POLYMERS
PORTLAND CEMENT
STABILITY
STRONTIUM 85
THERMAL CONDUCTIVITY
UREA
WASTE WATER
ALDEHYDES
ALKALI METAL ISOTOPES
ALKALINE EARTH ISOTOPES
AMIDES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CARBONIC ACID DERIVATIVES
CEMENTS
CESIUM ISOTOPES
CLEANING
COBALT ISOTOPES
DAYS LIVING RADIOISOTOPES
DISSOLUTION
ELECTRON CAPTURE RADIOISOTOPES
EVEN-ODD NUCLEI
HOURS LIVING RADIOISOTOPES
HYDROGEN COMPOUNDS
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
IRON ISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
LIQUID WASTES
MANAGEMENT
MATERIALS
MECHANICAL PROPERTIES
MINUTES LIVING RADIOISOTOPES
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
Colombo, P.
Neilson, R.M. Jr.
Properties of radioactive wastes and waste containers. Quarterly progress report, October--December 1976. [Urea-formaldehyde; polymer; portland cement]
topic_facet 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
RADIOACTIVE WASTE PROCESSING
SOLIDIFICATION
CESIUM 137
COBALT 60
COMPRESSION STRENGTH
DECONTAMINATION
EFFICIENCY
FORMALDEHYDE
IMPACT STRENGTH
IRON 59
LEACHING
POLYMERS
PORTLAND CEMENT
STABILITY
STRONTIUM 85
THERMAL CONDUCTIVITY
UREA
WASTE WATER
ALDEHYDES
ALKALI METAL ISOTOPES
ALKALINE EARTH ISOTOPES
AMIDES
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BUILDING MATERIALS
CARBONIC ACID DERIVATIVES
CEMENTS
CESIUM ISOTOPES
CLEANING
COBALT ISOTOPES
DAYS LIVING RADIOISOTOPES
DISSOLUTION
ELECTRON CAPTURE RADIOISOTOPES
EVEN-ODD NUCLEI
HOURS LIVING RADIOISOTOPES
HYDROGEN COMPOUNDS
INTERMEDIATE MASS NUCLEI
INTERNAL CONVERSION RADIOISOTOPES
IRON ISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPES
LIQUID WASTES
MANAGEMENT
MATERIALS
MECHANICAL PROPERTIES
MINUTES LIVING RADIOISOTOPES
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
description The cumulative quantities of free standing water resulting from the solidification of simulated wastes with urea-formaldehyde (UF) and portland type II cement were determined. The effect of the waste/solidification agent ratio on the cumulative free standing water for selected wastes solidified with UF was found to be related to sample shrinkage. Urea-formaldehyde decontamination factors for free standing water were determined with /sup 137/Cs, /sup 85/Sr, /sup 60/Co, and /sup 59/Fe. With the exception of /sup 85/Sr for which UF was shown to have a decontamination factor of 1.6-1.9, the specific activity of the free standing water was essentially equal to that of the waste prior to solidification. The release of cesium from UF in distilled water was measured by a static leaching technique. The effect of the leachant renewal interval and the ratio of the leachant volume (V/sub L/) to the sample external geometric surface area (S) was examined. The proposed leachant renewal interval of once/day and V/sub L/S = 10cm was found to be satisfactory for leaching of these samples. Samples of a proprietary polymer agent developed by the Dow Chemical Company were tested to determine water loss with exposure to ambient air, weight loss with temperature (TGA), thermal conductivity, compressive strength and impact strength. Property measurements were made for water/binder volume ratios of from 1.0 to 2.0. No deterioration was observed for a portland type II cement sample with a water/cement ratio of 0.5 by weight subjected to fifty freeze-thaw cycles.
author Colombo, P.
Neilson, R.M. Jr.
author_facet Colombo, P.
Neilson, R.M. Jr.
author_sort Colombo, P.
title Properties of radioactive wastes and waste containers. Quarterly progress report, October--December 1976. [Urea-formaldehyde; polymer; portland cement]
title_short Properties of radioactive wastes and waste containers. Quarterly progress report, October--December 1976. [Urea-formaldehyde; polymer; portland cement]
title_full Properties of radioactive wastes and waste containers. Quarterly progress report, October--December 1976. [Urea-formaldehyde; polymer; portland cement]
title_fullStr Properties of radioactive wastes and waste containers. Quarterly progress report, October--December 1976. [Urea-formaldehyde; polymer; portland cement]
title_full_unstemmed Properties of radioactive wastes and waste containers. Quarterly progress report, October--December 1976. [Urea-formaldehyde; polymer; portland cement]
title_sort properties of radioactive wastes and waste containers. quarterly progress report, october--december 1976. [urea-formaldehyde; polymer; portland cement]
publishDate 2012
url http://www.osti.gov/servlets/purl/7309235
https://www.osti.gov/biblio/7309235
https://doi.org/10.2172/7309235
genre Carbonic acid
genre_facet Carbonic acid
op_relation http://www.osti.gov/servlets/purl/7309235
https://www.osti.gov/biblio/7309235
https://doi.org/10.2172/7309235
doi:10.2172/7309235
op_doi https://doi.org/10.2172/7309235
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