Properties of radioactive wastes and waste containers. Quarterly progress report, January-March 1980
Solidification experiments were performed with organic ion-exchange resins using Portland type II cement to investigate waste to binder ratios which result in monolithic waste forms. Test results are provided in tabular form showing formulations which result in considerable swelling, cracking, or sp...
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ftosti:oai:osti.gov:5064936 2023-07-30T04:02:56+02:00 Properties of radioactive wastes and waste containers. Quarterly progress report, January-March 1980 Manaktala, H.K. Weiss, A.J. 2013-07-18 application/pdf http://www.osti.gov/servlets/purl/5064936 https://www.osti.gov/biblio/5064936 https://doi.org/10.2172/5064936 unknown http://www.osti.gov/servlets/purl/5064936 https://www.osti.gov/biblio/5064936 https://doi.org/10.2172/5064936 doi:10.2172/5064936 12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES LOW-LEVEL RADIOACTIVE WASTES SOLIDIFICATION WASTE FORMS RESEARCH PROGRAMS BORIC ACID EXPERIMENTAL DATA FORMALDEHYDE ION EXCHANGE MATERIALS PHASE DIAGRAMS PORTLAND CEMENT RESINS SODIUM HYDROXIDES UREA ALDEHYDES ALKALI METAL COMPOUNDS AMIDES BUILDING MATERIALS CARBONIC ACID DERIVATIVES CEMENTS DATA DIAGRAMS HYDROGEN COMPOUNDS HYDROXIDES INFORMATION INORGANIC ACIDS MATERIALS NUMERICAL DATA ORGANIC COMPOUNDS ORGANIC NITROGEN COMPOUNDS ORGANIC POLYMERS OXYGEN COMPOUNDS PETROCHEMICALS PETROLEUM PRODUCTS PHASE TRANSFORMATIONS POLYMERS RADIOACTIVE MATERIALS RADIOACTIVE WASTES SODIUM COMPOUNDS WASTES 2013 ftosti https://doi.org/10.2172/5064936 2023-07-11T10:36:22Z Solidification experiments were performed with organic ion-exchange resins using Portland type II cement to investigate waste to binder ratios which result in monolithic waste forms. Test results are provided in tabular form showing formulations which result in considerable swelling, cracking, or splitting of the specimens upon solidification. The range of waste loadings which produce monolithic waste forms is given. Experiments were conducted to establish appropriate waste/binder ratios within which simulated boric acid reactor waste may be incorporated into portland type III cement, to produce acceptable waste forms. Both pH-adjusted and pH-unadjusted boric acid solutions were used. Sodium hydroxide in solid pellet form was used to adjust the boric acid pH. Data are reported for 3, 6, and 12 weight percent boric acid wastes, with pH-adjusted values of 7, 10, and 12. Range of waste/binder ratios investigated is from 0.32 to 1.5. Results are summarized in the form of ternary compositional phase diagrams depicting envelope boundaries within which formulations exhibit no free standing liquids. The cure time is substantially reduced when NaOH pellets are used, rather than 10 M NaOH solution. This is attributed to the higher solid contents in the waste solution when NaOH in solid form is used. A ''two-part'' urea-formaldehyde process was used to solidify four simulated LWR waste streams, viz. ion-exchange bead resins, diatomaceous earth, sodium sulfate, and boric acid wastes. The waste forms were evaluated on the basis of solid monolith, free standing liquid, corrosivity of the free liquids, and specimen shrinkage criteria. The results show that the two-part urea-formaldehyde process (a) is capable of solidifying LWR low-level wastes into solid free-standing monoliths, (b) produces free-standing water with pH approximately 2, and (c) produces specimen shrinkage of approximately 5 volume percent after four weeks in an enclosed environment. Other/Unknown Material Carbonic acid SciTec Connect (Office of Scientific and Technical Information - OSTI, U.S. Department of Energy) Monolith ENVELOPE(163.283,163.283,-66.950,-66.950) |
institution |
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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 LOW-LEVEL RADIOACTIVE WASTES SOLIDIFICATION WASTE FORMS RESEARCH PROGRAMS BORIC ACID EXPERIMENTAL DATA FORMALDEHYDE ION EXCHANGE MATERIALS PHASE DIAGRAMS PORTLAND CEMENT RESINS SODIUM HYDROXIDES UREA ALDEHYDES ALKALI METAL COMPOUNDS AMIDES BUILDING MATERIALS CARBONIC ACID DERIVATIVES CEMENTS DATA DIAGRAMS HYDROGEN COMPOUNDS HYDROXIDES INFORMATION INORGANIC ACIDS MATERIALS NUMERICAL DATA ORGANIC COMPOUNDS ORGANIC NITROGEN COMPOUNDS ORGANIC POLYMERS OXYGEN COMPOUNDS PETROCHEMICALS PETROLEUM PRODUCTS PHASE TRANSFORMATIONS POLYMERS RADIOACTIVE MATERIALS RADIOACTIVE WASTES SODIUM COMPOUNDS WASTES |
spellingShingle |
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES LOW-LEVEL RADIOACTIVE WASTES SOLIDIFICATION WASTE FORMS RESEARCH PROGRAMS BORIC ACID EXPERIMENTAL DATA FORMALDEHYDE ION EXCHANGE MATERIALS PHASE DIAGRAMS PORTLAND CEMENT RESINS SODIUM HYDROXIDES UREA ALDEHYDES ALKALI METAL COMPOUNDS AMIDES BUILDING MATERIALS CARBONIC ACID DERIVATIVES CEMENTS DATA DIAGRAMS HYDROGEN COMPOUNDS HYDROXIDES INFORMATION INORGANIC ACIDS MATERIALS NUMERICAL DATA ORGANIC COMPOUNDS ORGANIC NITROGEN COMPOUNDS ORGANIC POLYMERS OXYGEN COMPOUNDS PETROCHEMICALS PETROLEUM PRODUCTS PHASE TRANSFORMATIONS POLYMERS RADIOACTIVE MATERIALS RADIOACTIVE WASTES SODIUM COMPOUNDS WASTES Manaktala, H.K. Weiss, A.J. Properties of radioactive wastes and waste containers. Quarterly progress report, January-March 1980 |
topic_facet |
12 MANAGEMENT OF RADIOACTIVE AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES LOW-LEVEL RADIOACTIVE WASTES SOLIDIFICATION WASTE FORMS RESEARCH PROGRAMS BORIC ACID EXPERIMENTAL DATA FORMALDEHYDE ION EXCHANGE MATERIALS PHASE DIAGRAMS PORTLAND CEMENT RESINS SODIUM HYDROXIDES UREA ALDEHYDES ALKALI METAL COMPOUNDS AMIDES BUILDING MATERIALS CARBONIC ACID DERIVATIVES CEMENTS DATA DIAGRAMS HYDROGEN COMPOUNDS HYDROXIDES INFORMATION INORGANIC ACIDS MATERIALS NUMERICAL DATA ORGANIC COMPOUNDS ORGANIC NITROGEN COMPOUNDS ORGANIC POLYMERS OXYGEN COMPOUNDS PETROCHEMICALS PETROLEUM PRODUCTS PHASE TRANSFORMATIONS POLYMERS RADIOACTIVE MATERIALS RADIOACTIVE WASTES SODIUM COMPOUNDS WASTES |
description |
Solidification experiments were performed with organic ion-exchange resins using Portland type II cement to investigate waste to binder ratios which result in monolithic waste forms. Test results are provided in tabular form showing formulations which result in considerable swelling, cracking, or splitting of the specimens upon solidification. The range of waste loadings which produce monolithic waste forms is given. Experiments were conducted to establish appropriate waste/binder ratios within which simulated boric acid reactor waste may be incorporated into portland type III cement, to produce acceptable waste forms. Both pH-adjusted and pH-unadjusted boric acid solutions were used. Sodium hydroxide in solid pellet form was used to adjust the boric acid pH. Data are reported for 3, 6, and 12 weight percent boric acid wastes, with pH-adjusted values of 7, 10, and 12. Range of waste/binder ratios investigated is from 0.32 to 1.5. Results are summarized in the form of ternary compositional phase diagrams depicting envelope boundaries within which formulations exhibit no free standing liquids. The cure time is substantially reduced when NaOH pellets are used, rather than 10 M NaOH solution. This is attributed to the higher solid contents in the waste solution when NaOH in solid form is used. A ''two-part'' urea-formaldehyde process was used to solidify four simulated LWR waste streams, viz. ion-exchange bead resins, diatomaceous earth, sodium sulfate, and boric acid wastes. The waste forms were evaluated on the basis of solid monolith, free standing liquid, corrosivity of the free liquids, and specimen shrinkage criteria. The results show that the two-part urea-formaldehyde process (a) is capable of solidifying LWR low-level wastes into solid free-standing monoliths, (b) produces free-standing water with pH approximately 2, and (c) produces specimen shrinkage of approximately 5 volume percent after four weeks in an enclosed environment. |
author |
Manaktala, H.K. Weiss, A.J. |
author_facet |
Manaktala, H.K. Weiss, A.J. |
author_sort |
Manaktala, H.K. |
title |
Properties of radioactive wastes and waste containers. Quarterly progress report, January-March 1980 |
title_short |
Properties of radioactive wastes and waste containers. Quarterly progress report, January-March 1980 |
title_full |
Properties of radioactive wastes and waste containers. Quarterly progress report, January-March 1980 |
title_fullStr |
Properties of radioactive wastes and waste containers. Quarterly progress report, January-March 1980 |
title_full_unstemmed |
Properties of radioactive wastes and waste containers. Quarterly progress report, January-March 1980 |
title_sort |
properties of radioactive wastes and waste containers. quarterly progress report, january-march 1980 |
publishDate |
2013 |
url |
http://www.osti.gov/servlets/purl/5064936 https://www.osti.gov/biblio/5064936 https://doi.org/10.2172/5064936 |
long_lat |
ENVELOPE(163.283,163.283,-66.950,-66.950) |
geographic |
Monolith |
geographic_facet |
Monolith |
genre |
Carbonic acid |
genre_facet |
Carbonic acid |
op_relation |
http://www.osti.gov/servlets/purl/5064936 https://www.osti.gov/biblio/5064936 https://doi.org/10.2172/5064936 doi:10.2172/5064936 |
op_doi |
https://doi.org/10.2172/5064936 |
_version_ |
1772813848472977408 |