Standard Test Method for Determination of Uranium Isotopic Composition by Modified Total Evaporation (MTE) Method Using Thermal Ionization Mass Spectrometer

SIGNIFICANCE AND USE
5.1 Uranium material is used as a fuel in certain types of nuclear reactors. To be suitable for use as nuclear fuel, the starting material shall meet certain specifications such as those described in Specifications C753, C776, C787, C833, C967, C996, and C1008, or as specified by the purchaser. The isotope amount ratios of uranium material can be measured by mass spectrometry following this test method to ensure that they meet the specification.  
5.2 The MTE method can be used for a wide range of sample sizes even in samples containing as low as 20 µg of uranium. If the uranium sample is in the form of uranium hexafluoride, it has to be converted into a uranium nitrate solution for measurement by the MTE method. The concentration of the loading solution for MTE has to be in the range of 1 mg/g to 6 mg/g to allow a sample loading of 2 µg to 6 µg of uranium. A minimum loading of 3 µg uranium per filament is strongly recommended. This is needed to have a sufficient and stable ion signal especially for the two minor isotopes (234U and 236U) thus enabling the internal calibration of SEM versus the Faraday cups using the 234U ion beam signal during the measurement.  
5.3 Until now, the instrument capabilities for the MTE method have only been implemented on the TRITON™ TIMS instrument.5 Therefore, all recommendations for measurement parameters in this test method are specified for the TRITON instrument. The manufacturers of other TIMS instruments (for example, IsotopX and Nu Instruments) have indicated plans to implement the modifications needed in their instruments to use the MTE method.  
5.4 The MTE method described here can also be extended to measurement of elements other than uranium. Note that the MTE method has already been implemented for plutonium and calcium.
SCOPE
1.1 This test method describes the determination of the isotope amount ratios of uranium material as nitrate solutions by the modified total evaporation (MTE) method using a thermal ionization mass spectrometer (TIMS) instrument.  
1.2 The analytical performance in the determination of the 235U/238U major isotope amount ratio by MTE is similar to the (“classical”) total evaporation (TE) method as described in C1672. However, in the MTE method, the evaporation process is interrupted on a regular basis to allow measurements and subsequent corrections for background from peak tailing, perform internal calibration of a secondary electron multiplier (SEM) detector versus the Faraday cups, peak centering, and ion source refocusing. Performing these calibrations and corrections on a regular basis during the measurement, improves precision, and significantly reduces uncertainties for the minor isotope amount ratios 234U/238U and 236U/238U as compared to the TE method.  
1.3 In principle, the MTE method may yield major isotope amount ratios without the need for mass fractionation correction. However, depending on the measurement conditions, small variations are observed between sample turrets. Therefore, a small correction based on measurements of a certified reference material is recommended to improve consistency. The uncertainty around the mass fractionation correction factor usually includes unity.  
1.4 Units—The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard.  
1.5 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.  
1.6 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 issu...

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Publication Date
31-Dec-2022
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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:C1832 −23
Standard Test Method for
Determination of Uranium Isotopic Composition by Modified
Total Evaporation (MTE) Method Using Thermal Ionization
1
Mass Spectrometer
This standard is issued under the fixed designation C1832; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope priate safety, health, and environmental practices and deter-
mine the applicability of regulatory limitations prior to use.
1.1 This test method describes the determination of the
1.6 This international standard was developed in accor-
isotope amount ratios of uranium material as nitrate solutions
dance with internationally recognized principles on standard-
by the modified total evaporation (MTE) method using a
ization established in the Decision on Principles for the
thermal ionization mass spectrometer (TIMS) instrument.
Development of International Standards, Guides and Recom-
1.2 The analytical performance in the determination of the
mendations issued by the World Trade Organization Technical
235 238
U/ U major isotope amount ratio by MTE is similar to the
Barriers to Trade (TBT) Committee.
(“classical”) total evaporation (TE) method as described in
C1672. However, in the MTE method, the evaporation process
2. Referenced Documents
is interrupted on a regular basis to allow measurements and 2
2.1 ASTM Standards:
subsequent corrections for background from peak tailing,
C753Specification for Nuclear-Grade, Sinterable Uranium
perform internal calibration of a secondary electron multiplier
Dioxide Powder
(SEM) detector versus the Faraday cups, peak centering, and
C776SpecificationforSinteredUraniumDioxidePelletsfor
ion source refocusing. Performing these calibrations and cor-
Light Water Reactors
rections on a regular basis during the measurement, improves
C787Specification for Uranium Hexafluoride for Enrich-
precision, and significantly reduces uncertainties for the minor
ment
234 238 236 238
isotope amount ratios U/ U and U/ U as compared to
C833Specification for Sintered (Uranium-Plutonium) Diox-
the TE method.
ide Pellets for Light Water Reactors
1.3 In principle, the MTE method may yield major isotope C859Terminology Relating to Nuclear Materials
C967Specification for Uranium Ore Concentrate
amount ratios without the need for mass fractionation correc-
tion. However, depending on the measurement conditions, C996Specification for Uranium Hexafluoride Enriched to
235
Less Than 5% U
small variations are observed between sample turrets.
Therefore, a small correction based on measurements of a C1008 Specification for Sintered (Uranium-Plutonium)
3
DioxidePellets—Fast Reactor Fuel (Withdrawn 2014)
certified reference material is recommended to improve con-
sistency.Theuncertaintyaroundthemassfractionationcorrec- C1068Guide for Qualification of Measurement Methods by
a Laboratory Within the Nuclear Industry
tion factor usually includes unity.
C1128Guide for Preparation of Working Reference Materi-
1.4 Units—The values stated in SI units are to be regarded
als for Use in Analysis of Nuclear Fuel Cycle Materials
as standard. The values given in parentheses after SI units are
C1156Guide for Establishing Calibration for a Measure-
providedforinformationonlyandarenotconsideredstandard.
ment Method Used toAnalyze Nuclear Fuel Cycle Mate-
1.5 This standard does not purport to address all of the
rials
safety concerns, if any, associated with its use. It is the
C1347Practice for Preparation and Dissolution of Uranium
responsibility of the user of this standard to establish appro-
Materials for Analysis
1 2
ThistestmethodisunderthejurisdictionofASTMCommitteeC26onNuclear For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Test. Standards volume information, refer to the standard’s Document Summary page on
Current edition approved Jan. 1, 2023. Published January 2023. Originally the ASTM website.
3
approved in 2016. Last previous edition approved in 2022 as C1832–22. DOI: The last approved version of this historical standard is referenced on
10.1520/C1832-23. www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1832−23
C1411Practice for The Ion Exchange Separation of Ura- 3
...

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: C1832 − 22 C1832 − 23
Standard Test Method for
Determination of Uranium Isotopic Composition by Modified
Total Evaporation (MTE) Method Using Thermal Ionization
1
Mass Spectrometer
This standard is issued under the fixed designation C1832; 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 This test method describes the determination of the isotope amount ratios of uranium material as nitrate solutions by the
modified total evaporation (MTE) method using a thermal ionization mass spectrometer (TIMS) instrument.
235 238
1.2 The analytical performance in the determination of the U/ U major isotope amount ratio by MTE is similar to the
(“classical”) total evaporation (TE) method as described in C1672. However, in the MTE method, the evaporation process is
interrupted on a regular basis to allow measurements and subsequent corrections for background from peak tailing, perform
internal calibration of a secondary electron multiplier (SEM) detector versus the Faraday cups, peak centering, and ion source
refocusing. Performing these calibrations and corrections on a regular basis during the measurement, improves precision, and
234 238 236 238
significantly reduces uncertainties for the minor isotope amount ratios U/ U and U/ U as compared to the TE method.
1.3 In principle, the MTE method may yield major isotope amount ratios without the need for mass fractionation correction.
However, depending on the measurement conditions, small variations are observed between sample turrets. Therefore, a small
correction based on measurements of a certified reference material is recommended to improve consistency. The uncertainty
around the mass fractionation correction factor usually includes unity.
1.4 Units—The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided
for information only and are not considered standard.
1.5 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.
1.6 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:
C753 Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
1
This test method is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of Test.
Current edition approved Feb. 1, 2022Jan. 1, 2023. Published March 2022January 2023. Originally approved in 2016. Last previous edition approved in 20212022 as
C1832 – 21.C1832 – 22. DOI: 10.1520/C1832-22.10.1520/C1832-23.
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 ----------------------
C1832 − 23
C776 Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors
C787 Specification for Uranium Hexafluoride for Enrichment
C833 Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors
C859 Terminology Relating to Nuclear Materials
C967 Specification for Uranium Ore Concentrate
235
C996 Specification for Uranium Hexafluoride Enriched to Less Than 5 % U
3
C1008 Specification for Sintered (Uranium-Plutonium) DioxidePellets—Fast Reactor Fuel (Withdrawn 2014)
C1068 Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry
C1128 Guide for Preparation of Working Reference Materials for Use in Analysis of Nuclear Fuel Cycle Materials
C1156 Guide for Establishing Calibration for a Measurement Method Used to Analyze Nuclear Fuel Cycle Materials
C1347 Pra
...

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