Properties of radioactive wastes and waste containers. Quarterly progress report, January--March 1977
The densities of the simulated wastes used in this program were determined and factors reported to allow conversion of formulation data for urea-formaldehyde (UF) waste forms from weight ratios to volume ratios of waste to UF. Simulated Solka-Floc wastes were solidified with urea-formaldehyde but ar...
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ftosti:oai:osti.gov:6567177 2023-07-30T04:02:56+02:00 Properties of radioactive wastes and waste containers. Quarterly progress report, January--March 1977 Colombo, P. Neilson, R.M. Jr. 2012-12-12 application/pdf http://www.osti.gov/servlets/purl/6567177 https://www.osti.gov/biblio/6567177 https://doi.org/10.2172/6567177 unknown http://www.osti.gov/servlets/purl/6567177 https://www.osti.gov/biblio/6567177 https://doi.org/10.2172/6567177 doi:10.2172/6567177 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES CESIUM 137 LEACHING CONTAINERS PERFORMANCE TESTING RADIOACTIVE WASTE PROCESSING SOLIDIFICATION RADIOACTIVE WASTES DENSITY STRONTIUM 85 CEMENTS FORMALDEHYDE RESEARCH PROGRAMS UREA ALDEHYDES ALKALI METAL ISOTOPES ALKALINE EARTH ISOTOPES AMIDES BETA DECAY RADIOISOTOPES BETA-MINUS DECAY RADIOISOTOPES BUILDING MATERIALS CARBONIC ACID DERIVATIVES CESIUM ISOTOPES DAYS LIVING RADIOISOTOPES DISSOLUTION ELECTRON CAPTURE RADIOISOTOPES EVEN-ODD NUCLEI HOURS LIVING RADIOISOTOPES INTERMEDIATE MASS NUCLEI ISOMERIC TRANSITION ISOTOPES ISOTOPES MANAGEMENT MATERIALS NUCLEI ODD-EVEN NUCLEI ORGANIC COMPOUNDS ORGANIC NITROGEN COMPOUNDS PHASE TRANSFORMATIONS PHYSICAL PROPERTIES PROCESSING RADIOACTIVE MATERIALS RADIOISOTOPES SEPARATION PROCESSES STRONTIUM ISOTOPES TESTING WASTE MANAGEMENT WASTE PROCESSING WASTES YEARS LIVING RADIOISOTOPES 2012 ftosti https://doi.org/10.2172/6567177 2023-07-11T10:49:42Z The densities of the simulated wastes used in this program were determined and factors reported to allow conversion of formulation data for urea-formaldehyde (UF) waste forms from weight ratios to volume ratios of waste to UF. Simulated Solka-Floc wastes were solidified with urea-formaldehyde but areas of unsolidified Solka-Floc were found in the final waste forms. The difficulty in mixing dewatered Solka-Floc waste with UF is presumed to be responsible. Attempts to solidify alkaline regenerative wastes with urea-formaldehyde were not successful. Increasing the waste/UF volume ratio to 3.0 produced acceptable solids with boric acid and decontamination waste, but not with chemical regenerative wastes. The use of masonry cement (one part Portland cement to one part anhydrous lime by weight) for the solidification of boric acid concentrate waste was investigated. Free standing solids were formed at waste/cement weight ratios of 0.6 and 1.0 but not at 1.5 or 2.0. Masonry cement was found to be superior to Portland cement for the solidification of boric acid wastes. The weight loss with temperature of urea-formaldehyde waste forms containing various simulated wastes was measured over the range of 25 to 500/sup 0/C. Weight losses due to the evaporation of water, decomposition of UF and decomposition of the wastes were observed. Static leaching experiments were conducted to determine the rate of release of cesium-137 and strontium-85 from urea-formaldehyde specimens and bead and powdered cation exchange resins. Results for the leaching of these materials in salt water, tap water, and distilled water are reported. Hydrostatic testing of modified DOT 17H open head 55 gallon drums was performed. These drums met the required DOT specifications and ultimately failed at an average pressure of 44 psig by separation of the drum head from the drum body at the gasket. Other/Unknown Material Carbonic acid SciTec Connect (Office of Scientific and Technical Information - OSTI, U.S. Department of Energy) Open Head ENVELOPE(-56.782,-56.782,49.800,49.800) |
institution |
Open Polar |
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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 CESIUM 137 LEACHING CONTAINERS PERFORMANCE TESTING RADIOACTIVE WASTE PROCESSING SOLIDIFICATION RADIOACTIVE WASTES DENSITY STRONTIUM 85 CEMENTS FORMALDEHYDE RESEARCH PROGRAMS UREA ALDEHYDES ALKALI METAL ISOTOPES ALKALINE EARTH ISOTOPES AMIDES BETA DECAY RADIOISOTOPES BETA-MINUS DECAY RADIOISOTOPES BUILDING MATERIALS CARBONIC ACID DERIVATIVES CESIUM ISOTOPES DAYS LIVING RADIOISOTOPES DISSOLUTION ELECTRON CAPTURE RADIOISOTOPES EVEN-ODD NUCLEI HOURS LIVING RADIOISOTOPES INTERMEDIATE MASS NUCLEI ISOMERIC TRANSITION ISOTOPES ISOTOPES MANAGEMENT MATERIALS NUCLEI ODD-EVEN NUCLEI ORGANIC COMPOUNDS ORGANIC NITROGEN COMPOUNDS PHASE TRANSFORMATIONS PHYSICAL PROPERTIES PROCESSING RADIOACTIVE MATERIALS RADIOISOTOPES SEPARATION PROCESSES STRONTIUM ISOTOPES TESTING WASTE MANAGEMENT WASTE PROCESSING WASTES YEARS LIVING RADIOISOTOPES |
spellingShingle |
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES CESIUM 137 LEACHING CONTAINERS PERFORMANCE TESTING RADIOACTIVE WASTE PROCESSING SOLIDIFICATION RADIOACTIVE WASTES DENSITY STRONTIUM 85 CEMENTS FORMALDEHYDE RESEARCH PROGRAMS UREA ALDEHYDES ALKALI METAL ISOTOPES ALKALINE EARTH ISOTOPES AMIDES BETA DECAY RADIOISOTOPES BETA-MINUS DECAY RADIOISOTOPES BUILDING MATERIALS CARBONIC ACID DERIVATIVES CESIUM ISOTOPES DAYS LIVING RADIOISOTOPES DISSOLUTION ELECTRON CAPTURE RADIOISOTOPES EVEN-ODD NUCLEI HOURS LIVING RADIOISOTOPES INTERMEDIATE MASS NUCLEI ISOMERIC TRANSITION ISOTOPES ISOTOPES MANAGEMENT MATERIALS NUCLEI ODD-EVEN NUCLEI ORGANIC COMPOUNDS ORGANIC NITROGEN COMPOUNDS PHASE TRANSFORMATIONS PHYSICAL PROPERTIES PROCESSING RADIOACTIVE MATERIALS RADIOISOTOPES SEPARATION PROCESSES STRONTIUM ISOTOPES TESTING WASTE MANAGEMENT WASTE PROCESSING WASTES YEARS LIVING RADIOISOTOPES Colombo, P. Neilson, R.M. Jr. Properties of radioactive wastes and waste containers. Quarterly progress report, January--March 1977 |
topic_facet |
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES CESIUM 137 LEACHING CONTAINERS PERFORMANCE TESTING RADIOACTIVE WASTE PROCESSING SOLIDIFICATION RADIOACTIVE WASTES DENSITY STRONTIUM 85 CEMENTS FORMALDEHYDE RESEARCH PROGRAMS UREA ALDEHYDES ALKALI METAL ISOTOPES ALKALINE EARTH ISOTOPES AMIDES BETA DECAY RADIOISOTOPES BETA-MINUS DECAY RADIOISOTOPES BUILDING MATERIALS CARBONIC ACID DERIVATIVES CESIUM ISOTOPES DAYS LIVING RADIOISOTOPES DISSOLUTION ELECTRON CAPTURE RADIOISOTOPES EVEN-ODD NUCLEI HOURS LIVING RADIOISOTOPES INTERMEDIATE MASS NUCLEI ISOMERIC TRANSITION ISOTOPES ISOTOPES MANAGEMENT MATERIALS NUCLEI ODD-EVEN NUCLEI ORGANIC COMPOUNDS ORGANIC NITROGEN COMPOUNDS PHASE TRANSFORMATIONS PHYSICAL PROPERTIES PROCESSING RADIOACTIVE MATERIALS RADIOISOTOPES SEPARATION PROCESSES STRONTIUM ISOTOPES TESTING WASTE MANAGEMENT WASTE PROCESSING WASTES YEARS LIVING RADIOISOTOPES |
description |
The densities of the simulated wastes used in this program were determined and factors reported to allow conversion of formulation data for urea-formaldehyde (UF) waste forms from weight ratios to volume ratios of waste to UF. Simulated Solka-Floc wastes were solidified with urea-formaldehyde but areas of unsolidified Solka-Floc were found in the final waste forms. The difficulty in mixing dewatered Solka-Floc waste with UF is presumed to be responsible. Attempts to solidify alkaline regenerative wastes with urea-formaldehyde were not successful. Increasing the waste/UF volume ratio to 3.0 produced acceptable solids with boric acid and decontamination waste, but not with chemical regenerative wastes. The use of masonry cement (one part Portland cement to one part anhydrous lime by weight) for the solidification of boric acid concentrate waste was investigated. Free standing solids were formed at waste/cement weight ratios of 0.6 and 1.0 but not at 1.5 or 2.0. Masonry cement was found to be superior to Portland cement for the solidification of boric acid wastes. The weight loss with temperature of urea-formaldehyde waste forms containing various simulated wastes was measured over the range of 25 to 500/sup 0/C. Weight losses due to the evaporation of water, decomposition of UF and decomposition of the wastes were observed. Static leaching experiments were conducted to determine the rate of release of cesium-137 and strontium-85 from urea-formaldehyde specimens and bead and powdered cation exchange resins. Results for the leaching of these materials in salt water, tap water, and distilled water are reported. Hydrostatic testing of modified DOT 17H open head 55 gallon drums was performed. These drums met the required DOT specifications and ultimately failed at an average pressure of 44 psig by separation of the drum head from the drum body at the gasket. |
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, January--March 1977 |
title_short |
Properties of radioactive wastes and waste containers. Quarterly progress report, January--March 1977 |
title_full |
Properties of radioactive wastes and waste containers. Quarterly progress report, January--March 1977 |
title_fullStr |
Properties of radioactive wastes and waste containers. Quarterly progress report, January--March 1977 |
title_full_unstemmed |
Properties of radioactive wastes and waste containers. Quarterly progress report, January--March 1977 |
title_sort |
properties of radioactive wastes and waste containers. quarterly progress report, january--march 1977 |
publishDate |
2012 |
url |
http://www.osti.gov/servlets/purl/6567177 https://www.osti.gov/biblio/6567177 https://doi.org/10.2172/6567177 |
long_lat |
ENVELOPE(-56.782,-56.782,49.800,49.800) |
geographic |
Open Head |
geographic_facet |
Open Head |
genre |
Carbonic acid |
genre_facet |
Carbonic acid |
op_relation |
http://www.osti.gov/servlets/purl/6567177 https://www.osti.gov/biblio/6567177 https://doi.org/10.2172/6567177 doi:10.2172/6567177 |
op_doi |
https://doi.org/10.2172/6567177 |
_version_ |
1772813848647041024 |