ASTM C1463-19
(Practice)Standard Practices for Dissolving Glass Containing Radioactive and Mixed Waste for Chemical and Radiochemical Analysis
Standard Practices for Dissolving Glass Containing Radioactive and Mixed Waste for Chemical and Radiochemical Analysis
ABSTRACT
These practices cover three standard technique for dissolving glass samples containing radioactive, nuclear, and mixed wastes. These techniques used together or independently will produce solutions that can be analyzed by inductively coupled plasma atomic emission spectroscopy (ICP-AES), inductively coupled plasma mass spectrometry (ICP-MS), atomic absorption spectrometry (AAS), radiochemical methods and wet chemical techniques for major components, minor components and radionuclides. The practices for dissolving silicate matrix samples each require the sample to be initially dried and ground to a fine powder. The first practice involves the mixing and fusion of the sample with sodium tetraborate (Na2B4O7) and sodium carbonate (Na2CO4) in a muffle for a given amount of time and temperature. The sample is then cooled, dissolved in hydrochloric acid, and diluted to appropriate volume for analyses. The second practice, on the other hand, involves the fusion of the sample with potassium hydroxide (KOH) or sodium peroxide (Na2O2) using an electric bunsen burner, dissolving the fused sample in water and dilute HCl, and making to volume for analyses. Finally, the third practice involves the dissolution of the sample using a microwave oven. The ground sample is digested in a microwave oven using a mixture of hydrofluoric (HF) and nitric (HNO3) acids. Boric acid is added to the resulting solution to complex excess fluoride ions.
SCOPE
1.1 These practices cover techniques suitable for dissolving glass samples that may contain nuclear wastes. These techniques used together or independently will produce solutions that can be analyzed by inductively coupled plasma atomic emission spectroscopy (ICP-AES), inductively coupled plasma mass spectrometry (ICP-MS), atomic absorption spectrometry (AAS), radiochemical methods and wet chemical techniques for major components, minor components and radionuclides.
1.2 One of the fusion practices and the microwave practice can be used in hot cells and shielded hoods after modification to meet local operational requirements.
1.3 The user of these practices must follow radiation protection guidelines in place for their specific laboratories.
1.4 Additional information relating to safety is included in the text.
1.5 The dissolution techniques described in these practices can be used for quality control of the feed materials and the product of plants vitrifying nuclear waste materials in glass.
1.6 These practices are introduced to provide the user with an alternative means to Test Methods C169 for dissolution of waste containing glass in shielded facilities. Test Methods C169 is not practical for use in such facilities and with radioactive materials.
1.7 The ICP-AES methods in Test Methods C1109 and C1111 can be used to analyze the dissolved sample with additional sample preparation as necessary and with matrix effect considerations. Additional information as to other analytical methods can be found in Test Method C169.
1.8 Solutions from this practice may be suitable for analysis using ICP-MS after establishing laboratory performance criteria and verification that the criteria can be met. For example, Test Methods C1287 or C1637 may be used with additional sample preparation as necessary and appropriate matrix effect considerations.
1.9 The values stated in SI units are to be regarded as standard. Units in parentheses are for information only.
1.10 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. Specific precautionary statements are given in Sections 10, 20, and 30.
1.11 This international standard was developed in accordance with internationally recognized principles on standardization established in the De...
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Standards Content (Sample)
This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the
Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
Designation: C1463 − 19
Standard Practices for
Dissolving Glass Containing Radioactive and Mixed Waste
1
for Chemical and Radiochemical Analysis
This standard is issued under the fixed designation C1463; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope Test Methods C1287 or C1637 may be used with additional
sample preparation as necessary and appropriate matrix effect
1.1 These practices cover techniques suitable for dissolving
considerations.
glass samples that may contain nuclear wastes. These tech-
1.9 The values stated in SI units are to be regarded as
niques used together or independently will produce solutions
standard. Units in parentheses are for information only.
that can be analyzed by inductively coupled plasma atomic
emission spectroscopy (ICP-AES), inductively coupled plasma
1.10 This standard does not purport to address all of the
mass spectrometry (ICP-MS), atomic absorption spectrometry
safety concerns, if any, associated with its use. It is the
(AAS), radiochemical methods and wet chemical techniques
responsibility of the user of this standard to establish appro-
for major components, minor components and radionuclides.
priate safety, health, and environmental practices and deter-
mine the applicability of regulatory limitations prior to use.
1.2 One of the fusion practices and the microwave practice
Specific precautionary statements are given in Sections 10, 20,
can be used in hot cells and shielded hoods after modification
and 30.
to meet local operational requirements.
1.11 This international standard was developed in accor-
1.3 The user of these practices must follow radiation pro-
dance with internationally recognized principles on standard-
tection guidelines in place for their specific laboratories.
ization established in the Decision on Principles for the
Development of International Standards, Guides and Recom-
1.4 Additional information relating to safety is included in
mendations issued by the World Trade Organization Technical
the text.
Barriers to Trade (TBT) Committee.
1.5 The dissolution techniques described in these practices
can be used for quality control of the feed materials and the
2. Referenced Documents
product of plants vitrifying nuclear waste materials in glass.
2
2.1 ASTM Standards:
1.6 These practices are introduced to provide the user with
C169 Test Methods for Chemical Analysis of Soda-Lime
an alternative means to Test Methods C169 for dissolution of
and Borosilicate Glass
waste containing glass in shielded facilities. Test Methods
C859 Terminology Relating to Nuclear Materials
C169 is not practical for use in such facilities and with C1109 Practice for Analysis of Aqueous Leachates from
radioactive materials.
Nuclear Waste Materials Using Inductively Coupled
Plasma-Atomic Emission Spectroscopy
1.7 The ICP-AES methods in Test Methods C1109 and
C1111 Test Method for Determining Elements in Waste
C1111 can be used to analyze the dissolved sample with
StreamsbyInductivelyCoupledPlasma-AtomicEmission
additional sample preparation as necessary and with matrix
Spectroscopy
effect considerations. Additional information as to other ana-
C1220 Test Method for Static Leaching of MonolithicWaste
lytical methods can be found in Test Method C169.
Forms for Disposal of Radioactive Waste
1.8 Solutions from this practice may be suitable for analysis
C1285 Test Methods for Determining Chemical Durability
using ICP-MS after establishing laboratory performance crite-
of Nuclear, Hazardous, and Mixed Waste Glasses and
ria and verification that the criteria can be met. For example,
MultiphaseGlassCeramics:TheProductConsistencyTest
(PCT)
C1287 Test Method for Determination of Impurities in
1
These practices are under the jurisdiction ofASTM Committee C26 on Nuclear
Fuel Cycle and are the direct responsibility of Subcommittee C26.05 on Methods of
2
Test. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved Feb. 1, 2019. Published February 2019. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 2000. Last previous edition approved in 2013 as C1463 – 13. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/C1463-19. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
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This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation: C1463 − 13 C1463 − 19
Standard Practices for
Dissolving Glass Containing Radioactive and Mixed Waste
1
for Chemical and Radiochemical Analysis
This standard is issued under the fixed designation C1463; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope
1.1 These practices cover techniques suitable for dissolving glass samples that may contain nuclear wastes. These techniques
used together or independently will produce solutions that can be analyzed by inductively coupled plasma atomic emission
spectroscopy (ICP-AES), inductively coupled plasma mass spectrometry (ICP-MS), atomic absorption spectrometry (AAS),
radiochemical methods and wet chemical techniques for major components, minor components and radionuclides.
1.2 One of the fusion practices and the microwave practice can be used in hot cells and shielded hoods after modification to
meet local operational requirements.
1.3 The user of these practices must follow radiation protection guidelines in place for their specific laboratories.
1.4 Additional information relating to safety is included in the text.
1.5 The dissolution techniques described in these practices can be used for quality control of the feed materials and the product
of plants vitrifying nuclear waste materials in glass.
1.6 These practices are introduced to provide the user with an alternative means to Test Methods C169 for dissolution of waste
containing glass in shielded facilities. Test Methods C169 is not practical for use in such facilities and with radioactive materials.
1.7 The ICP-AES methods in Test Methods C1109 and C1111 can be used to analyze the dissolved sample with additional
sample preparation as necessary and with matrix effect considerations. Additional information as to other analytical methods can
be found in Test Method C169.
1.8 Solutions from this practice may be suitable for analysis using ICP-MS after establishing laboratory performance
criteria.criteria and verification that the criteria can be met. For example, Test Methods C1287 or C1637 may be used with
additional sample preparation as necessary and appropriate matrix effect considerations.
1.9 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this
standard.Units in parentheses are for information only.
1.10 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility
of the user of this standard to establish appropriate safety safety, health, and healthenvironmental practices and determine the
applicability of regulatory limitations prior to use. Specific precautionary statements are given in Sections 10, 20, and 30.
1.11 This international standard was developed in accordance with internationally recognized principles on standardization
established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued
by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
2. Referenced Documents
2
2.1 ASTM Standards:
C169 Test Methods for Chemical Analysis of Soda-Lime and Borosilicate Glass
C859 Terminology Relating to Nuclear Materials
C1109 Practice for Analysis of Aqueous Leachates from Nuclear Waste Materials Using Inductively Coupled Plasma-Atomic
Emission Spectroscopy
C1111 Test Method for Determining Elements in Waste Streams by Inductively Coupled Plasma-Atomic Emission Spectroscopy
1
These practices are under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and are the direct responsibility of Subcommittee C26.05 on Methods of Test.
Current edition approved July 1, 2013Feb. 1, 2019. Published July 2013February 2019. Originally approved in 2000. Last previous edition approved in 20072013 as
C1463 – 00 (2007).C1463 – 13. DOI: 10.1520/C1463-13.10.1520/C1463-19.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C1463 − 19
C1220 Test Method for
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