ASTM C1880-19
(Practice)Standard Practice for Sampling Gaseous Uranium Hexafluoride using Alumina Pellets
Standard Practice for Sampling Gaseous Uranium Hexafluoride using Alumina Pellets
SIGNIFICANCE AND USE
5.1 Facility operators and safeguards inspectors routinely take UF6 samples from processing lines, isotopic enrichment cascades or storage cylinders to determine its U isotopic composition, most important the n(235U)/n(238U) isotope ratio, needed to calculate the amount of the fissile 235U in the sample. The current version of the “International Target Values for Measurement Uncertainties in Safeguarding Nuclear Materials” (3) contains recommended guidelines for these measurements.
5.2 The conventional sampling practice collects UF6 samples in the range of 1-10 g and requires the use of liquid nitrogen to condense them in sample vessels, metallic bottles or P-10 tubes. These samples must then be transported to external analytical laboratories for verification of the declared data, especially the isotope ratios. Transport includes, among other things, public roads and intercontinental air shipment. Due to the hazards of UF6, air transport is becoming increasingly difficult, with many transport operators and regulators refusing to carry the material.
5.3 This sampling practice was developed to meet the following requirements:
5.3.1 Fit for Purpose: to enable the verification of the declarations of amounts of nuclear materials.
5.3.2 Simplicity: to ensure a simple and fast execution.
5.3.3 Flexibility: to be applied in a wide range of facilities.
5.3.4 Robustness: to ensure sufficient material is sampled even when operational parameters slightly change.
5.3.5 Reliability: to provide measurement results in agreement with those obtained using the conventional sampling practice.
5.3.6 Confidentiality: to respect the facility’s operational procedure and confidentiality of data.
5.3.7 Safety: to reduce the risks associated with the sampling, handling and transport of radioactive and hazardous materials.
5.4 This sampling practice offers significant advantages over the conventional sampling practice because it allows handling non-reactive, non-v...
SCOPE
1.1 This practice is applicable to sampling gaseous uranium hexafluoride (UF6) from processing facilities, isotope enrichment cascades or storage cylinders, using the sorbent properties of aluminum oxide (Al2O3).
1.2 It is based on the ‘ABACC-Cristallini Method’ (1, 2)2 and is intended to be used for the determination of uranium (U) isotopic composition required for nuclear material safeguards as well as other applications.
1.3 The application of this practice assures the resulting sample vessel contains no UF6 and hydrogen fluoride (HF); therefore, it may be handled and categorized for transport under less stringent constraints.
1.4 The scope of this practice does not include provisions for preventing criticality.
1.5 Units—The values stated in SI units are to be regarded as the standard. When non-SI units are provided, they are for information only.
1.6 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.
1.7 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.
General Information
Relations
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: C1880 −19
Standard Practice for
Sampling Gaseous Uranium Hexafluoride using Alumina
1
Pellets
This standard is issued under the fixed designation C1880; 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 2. Referenced Documents
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1.1 This practice is applicable to sampling gaseous uranium 2.1 ASTM Standards:
hexafluoride (UF ) from processing facilities, isotope enrich-
C761 Test Methods for Chemical, Mass Spectrometric,
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ment cascades or storage cylinders, using the sorbent proper-
Spectrochemical, Nuclear, and RadiochemicalAnalysis of
ties of aluminum oxide (Al O ).
Uranium Hexafluoride
2 3
2
C787 Specification for Uranium Hexafluoride for Enrich-
1.2 It is based on the ‘ABACC-Cristallini Method’ (1, 2)
ment
andisintendedtobeusedforthedeterminationofuranium(U)
C859 Terminology Relating to Nuclear Materials
isotopic composition required for nuclear material safeguards
C996 Specification for Uranium Hexafluoride Enriched to
as well as other applications.
235
Less Than 5 % U
1.3 The application of this practice assures the resulting
C1052 Practice for Bulk Sampling of Liquid Uranium
sample vessel contains no UF and hydrogen fluoride (HF);
6
Hexafluoride
therefore, it may be handled and categorized for transport
C1346 Practice for Dissolution of UF from P-10 Tubes
6
under less stringent constraints.
C1474 Test Method forAnalysis of Isotopic Composition of
1.4 The scope of this practice does not include provisions Uranium in Nuclear-Grade Fuel Material by Quadrupole
for preventing criticality. Inductively Coupled Plasma-Mass Spectrometry
C1477 Test Method for Isotopic Abundance Analysis of
1.5 Units—The values stated in SI units are to be regarded
Uranium Hexafluoride and Uranyl Nitrate Solutions by
as the standard. When non-SI units are provided, they are for
Multi-Collector, Inductively Coupled Plasma-Mass Spec-
information only.
trometry
1.6 This standard does not purport to address all of the
C1672 Test Method for Determination of Uranium or Pluto-
safety concerns, if any, associated with its use. It is the
nium Isotopic Composition or Concentration by the Total
responsibility of the user of this standard to establish appro-
Evaporation Method Using a Thermal Ionization Mass
priate safety, health, and environmental practices and deter-
Spectrometer
mine the applicability of regulatory limitations prior to use.
C1703 Practice for Sampling of Gaseous Uranium
1.7 This international standard was developed in accor-
Hexafluoride for Enrichment
dance with internationally recognized principles on standard-
C1832 Test Method for Determination of Uranium Isotopic
ization established in the Decision on Principles for the
Composition by the Modified Total Evaporation (MTE)
Development of International Standards, Guides and Recom-
Method Using a Thermal Ionization Mass Spectrometer
mendations issued by the World Trade Organization Technical
C1871 Test Method for Determination of Uranium Isotopic
Barriers to Trade (TBT) Committee.
Composition by the Double Spike Method Using a Ther-
mal Ionization Mass Spectrometer
D1193 Specification for Reagent Water
1
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and
Fertile Material Specifications.
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Current edition approved June 1, 2019. Published July 2019. DOI: 10.1520/ For referenced ASTM standards, visit the ASTM website, www.astm.org, or
C1880-19. contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
2
The boldface numbers in parentheses refer to a list of references at the end of Standards volume information, refer to the standard’s Document Summary page on
this standard. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
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C1880 − 19
2.2 Other Documents: pressure, temperature and exposure time. The maximum ad-
USEC-651 Revision 10 The UF Manual – Good Handling sorption capacity is approximately 600 mg of U per gram of
6
4
Practices for Uranium Hexafluoride alumina.
IAEA-TECDOC-771 ManualonSafeProduction,Transport,
4.6 At the analytical laboratory, the alumina pellets are
5
Handling and Storage of Uranium Hexafluoride
transferred from the P-10 tube to an Erlenmeyer flask and
leached initially with distilled water and finally with nitric acid
3. Termin
...
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