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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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) |
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SciTec Connect (Office of Scientific and Technical Information - OSTI, U.S. Department of Energy) |
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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 |
_version_ |
1772813845993095168 |