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

Status
Published
Publication Date
31-May-2019
Technical Committee
C26 - Nuclear Fuel Cycle

Relations

Effective Date
01-Jan-2024
Effective Date
01-Dec-2023
Effective Date
01-Jul-2020
Effective Date
01-Mar-2020
Effective Date
01-Mar-2020
Effective Date
01-Nov-2019
Effective Date
01-Feb-2019
Effective Date
01-Feb-2019
Effective Date
01-Feb-2018
Effective Date
01-Feb-2018
Effective Date
01-Jan-2017
Effective Date
01-Jul-2015
Effective Date
01-Jul-2015
Effective Date
15-Jun-2014
Effective Date
15-Jan-2014

Overview

ASTM C1880-19: Standard Practice for Sampling Gaseous Uranium Hexafluoride using Alumina Pellets provides an internationally recognized procedure for the safe, efficient, and reliable sampling of gaseous uranium hexafluoride (UF6) in nuclear facilities. Developed under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle, this standard is a significant step forward in nuclear material safeguards, isotopic composition determination, and compliance with international measurement uncertainty guidelines.

By using the alumina (Al2O3) pellet method, this standard enables facility operators and nuclear safeguards inspectors to collect UF6 samples from processing lines, isotope enrichment cascades, or storage cylinders. The technique ensures simplified handling and transport, improved safety, and enhanced flexibility compared to traditional methods.

Key Topics

  • Scope: ASTM C1880-19 applies to the sampling of gaseous UF6 for isotopic analysis, especially the critical n(235U)/n(238U) ratio, which is essential for determining the quantity of fissile material.
  • Methodology: The standard utilizes the sorbent properties of aluminum oxide pellets based on the ABACC-Cristallini Method to convert volatile UF6 into a stable, non-volatile uranyl fluoride (UO2F2) form.
  • Sample Handling: Post-sampling, vessels contain no UF6 or hydrogen fluoride (HF), allowing for safer and less restricted transport and handling.
  • Advantages:
    • Minimized radiological and chemical hazards
    • Compatibility with a wide range of facilities and operational conditions
    • Simple, robust, and reliable procedure that aligns with nuclear material safeguards requirements
    • Enhanced transportability due to reduction of risk factors
  • Confidentiality and Safety: The procedure ensures adherence to facility confidentiality and significantly reduces exposure risks during sampling and shipping.

Applications

The ASTM C1880-19 standard practice is widely applicable in:

  • Nuclear Material Safeguards: Enabling verification of facility declarations regarding uranium content and enrichment.
  • Isotopic Analysis: Providing accurate, reliable samples for laboratory analysis using mass spectrometric and radiochemical methods to determine uranium isotope ratios.
  • International Safeguards Compliance: Meeting International Atomic Energy Agency (IAEA) recommendations for measurement uncertainty and procedures.
  • Transport and Storage: Offering substantial safety improvements by converting UF6 into a non-volatile, less hazardous form, making it suitable for public road and air transport under fewer regulatory constraints.
  • Flexible Facility Operations: Supporting use in a broad spectrum of enrichment, processing, and storage facilities without compromising reliability or data confidentiality.

Related Standards

ASTM C1880-19 references several other key ASTM standards relevant to nuclear fuel cycle operations and uranium analysis:

  • ASTM C761: Test methods for chemical, mass spectrometric, and nuclear analysis of uranium hexafluoride
  • ASTM C787 and C996: Specifications for various enrichments of uranium hexafluoride
  • ASTM C1052, C1346, and C1703: Practices for sampling and dissolution of uranium hexafluoride
  • ASTM C1474, C1477, C1672, C1832, and C1871: Test methods for uranium isotopic determination using mass spectrometric techniques
  • ASTM D1193: Specifications for reagent water used in analytical operations

These related standards ensure consistency and compatibility when conducting uranium sampling, analysis, and reporting for nuclear safeguards and industry-specific applications.

Practical Value

ASTM C1880-19 is essential for nuclear fuel cycle operators, regulatory bodies, and analytical laboratories tasked with uranium sampling and isotope ratio determination. By enhancing safety and simplifying logistics, this standard directly supports international non-proliferation efforts and compliance with quality and safety standards across the nuclear industry. Adopting this alumina pellet sampling practice results in improved efficiency, minimized risk, and reliable analytical outcomes for critical isotopic measurements in nuclear material safeguards.

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Frequently Asked Questions

ASTM C1880-19 is a standard published by ASTM International. Its full title is "Standard Practice for Sampling Gaseous Uranium Hexafluoride using Alumina Pellets". This standard covers: 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.

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.

ASTM C1880-19 is classified under the following ICS (International Classification for Standards) categories: 27.120.30 - Fissile materials and nuclear fuel technology. The ICS classification helps identify the subject area and facilitates finding related standards.

ASTM C1880-19 has the following relationships with other standards: It is inter standard links to ASTM C859-24, ASTM C1672-23, ASTM C1052-20, ASTM C787-20, ASTM C996-20, ASTM C1477-19, ASTM C1474-19, ASTM C1346-19, ASTM C1871-18, ASTM C761-18, ASTM C1672-17, ASTM C787-15, ASTM C996-15, ASTM C859-14a, ASTM C859-14. Understanding these relationships helps ensure you are using the most current and applicable version of the standard.

ASTM C1880-19 is available in PDF format for immediate download after purchase. The document can be added to your cart and obtained through the secure checkout process. Digital delivery ensures instant access to the complete standard document.

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
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
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,
ment cascades or storage cylinders, using the sorbent proper-
Spectrochemical, Nuclear, and RadiochemicalAnalysis of
ties of aluminum oxide (Al O ).
Uranium Hexafluoride
2 3
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.
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);
Hexafluoride
therefore, it may be handled and categorized for transport
C1346 Practice for Dissolution of UF from P-10 Tubes
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
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.
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
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
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
Practices for Uranium Hexafluoride alumina.
IAEA-TECDOC-771 ManualonSafeProduction,Transport,
4.6 At the analytical laboratory, the alumina pellets are
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. Terminology
(HNO ). The alumina fines produced must be carefully re-
3.1 Terminology C859 contains terms, definitions, descrip-
moved from the solution so that it can be prepared for the
tions of terms, nomenclature, and explanations of acronyms
determination of the U isotopic composition using, for
and symbols specifically associated with standards under the
example, Test Methods C1672, C1832, C1871, C1474,or
jurisdiction of Committee C26 on Nuclear Fuel Cycle.
C1477.
3.2 Definitions of Terms Specific to This Standard:
5. Significance and Use
3.2.1 sample vessel—the small vessel, for example a P-10
tube, into which the UF sample is transferred and stored for
6 5.1 Facility operators and safeguards inspectors routinely
characterization in the analytical laboratory. It can be made of
take UF samples from processing lines, isotopic enrichment
polychlorotrifluorethylene (PCTFE), polytetrafluoroethylene
cascades or storage cylinders to determine its U isotopic
235 238
(PTFE) or any other material chemically resistant to UF . The
composition, most important the n( U)/n( U) isotope ratio,
dimensions of the P-10 tube and its components, gasket, nut
neededtocalculatetheamountofthefissile Uinthesample.
and plug, can be found in Practice C1346.
The current version of the “International Target Values for
3.2.2 sampling manifold—a set-up used to connect the Measurement Uncertainties in Safeguarding Nuclear Materi-
als” (3) contains recommended guidelines for these measure-
sample vessel to the UF processing lines, isotope enrichment
cascades or storage cylinders, allowing vacuum pumping or ments.
pressurization by the introduction of an inert gas.
5.2 The conventional sampling practice collects UF
samples in the range of 1-10 g and requires the use of liquid
4. Summary of Practice
nitrogen to condense them in sample vessels, metallic bottles
4.1 A tared P-10 tube filled with a weighed quantity of
or P-10 tubes. These samples must then be transported to
aluminum oxide (Al O ) pellets, hereafter referred to as
external analytical laboratories for verification of the declared
2 3
alumina, is attached to a sampling manifold, and exposed to
data, especially the isotope ratios. Transport includes, among
gaseous UF for a timed period, typically 10 to 30 min,
other things, public roads and intercontinental air shipment.
depending on the gas pressure in the facility and the desired
Due to the hazards of UF , air transport is becoming increas-
amount of U amount to be deposited in the P-10 tube. UF
ingly difficult, with many transport operators and regulators
readily reacts in contact with alumina pellets generating
refusing to carry the material.
predominantly uranyl fluoride (UO F ).
2 2
5.3 This sampling practice was developed to meet the
4.2 When the sampling period is over, the P-10 tube and the
following requirements:
manifold are evacuated to remove remaining gaseous com-
5.3.1 Fit for Purpose: to enable the verification of the
pounds. Next, the valve that connects the manifold to the
declarations of amounts of nuclear materials.
processinglineisclosedandtheP-10tubeandthemanifoldare
5.3.2 Simplicity: to ensure a simple and fast execution.
pressurized to atmospheric pressure with dry nitrogen (N)to
5.3.3 Flexibility: to be applied in a wide range of facilities.
prevent moisture build-up within them.
5.3.4 Robustness: to ensure sufficient material is sampled
4.3 These evacuation and pressurization operations must be even when operational parameters slightly change.
repeated twice to assure no UF or HF is present in the vessel,
5.3.5 Reliability: to provide measurement results in agree-
but only solid UO F on the alumina support.This is of utmost
ment with those obtained using the conventional sampling
2 2
importance to achieve a less stringent sample vessel categori-
practice.
zation for transport.
5.3.6 Confidentiality: to respect the facility’s operational
procedure and confidentiality of data.
4.4 The P-10 tube can now be safely removed from the
5.3.7 Safety: to reduce the risks associated with the
manifold and sealed. The amount of U in the P-10 tube can be
sampling, handling and transport of radioactive and hazardous
determined by re-weighing the P-10 tube.
materials.
4.5 Using a P-10 tube loaded with1gof alumina pellets,
5.4 This sampling practice offers significant advantages
and sampling from UF processing lines, enrichment cascades
or storage cylinders under typical conditions will easily allow over the conventional sampling practice because it allows
handling non-reactive, non-volatile, solid UO F instead of
the adsorption of 100 to 300 mg of U, based on the gas
2 2
highly reactive and volatile UF .
5.5 A smaller UO F sample can be transported with lower
2 2
Available from Centrus Energy Corp., 6901 Rockledge Drive, Bethesda, MD
radioactivitylevelandreducedradiologicalproblemsincaseof
20817, http://centrusenergy.com.
accident. Additionally, there is no risk of airborne uranium
Available from International Atomic Energy Agency (IAEA), Vienna Interna-
tional Center, PO Box 100, A-1400 Vienna, Austria, http://www.iaea.org. particle and HF release.
C1880 − 19
5.6 The U isotope ratios measured in UF sampled by the be difficult to reduce the pressure in the manifold and in the
conventional and this sampling practice provide measurement P-10 tube to at least 10 Pa, and moisture may be introduced
results which are in good agreement within the stated uncer- into the processing line.
tainties (4, 5).
6.3 Purity of Water—Unless otherwise indicated, references
5.7 ItisstronglyrecommendedtodiscardusedP-10tubesto
to water should be understood to mean laboratory accepted
avoid the possibility of isotopic cross contamination, mainly
demineralized or deionized water as described by Type I of
because this practice is associated with the processing of very
Specification D1193.
small amounts of U.
6.4 HNO , concentrated acid, specific gravity 1.42, 15.8M.
5.8 In case recycled P-10 tubes are used, a very efficient and
6.5 HNO , 0.3M: add approximately 18 mLof concentrated
reliable cleaning procedure must be employed to assure a
HNO to 500 mL of water and dilute to 1 L.
complete removal of U from the P-10 tube inner surfaces.
6.6 HNO , 4-8 M: add approximately 250-500 mL of
5.9 This practice provides guidance to obtain samples for
concentrated HNO to 400 mL of water and dilute to 1 L.
determining the U composition for material nuclear safeguards
as well as other applications. Such samples should not be used
6.7 Dry N Gas, purity grade 99.5 %, water content lower
for determining compliance with Specifications C787 and
than 10 ppm.
C996. For these cases, the recommendations of Practices
C1052 or C1703 must be followed.
7. Hazards
5.10 The test methods describing procedures for
7.1 UF is radioactive, corrosive, toxic and highly reactive.
subsampling, mass spectrometric, spectrochemical, nuclear,
At ambient conditions it is a nearly white crystalline solid with
and radiochemical analysis of uranium hexafluoride are pre-
high vapor pressure. Its reaction with H O is exothermic and
sented in Test Methods C761. Most of them are routinely used
generates corrosive HF and toxic UO F . It attacks most
2 2
to determine the compliance with Specifications C787 and
metals, some plastics, rubber and coatings. It is also incompat-
C996.
ible with aromatic hydrocarbons and hydroxy compounds.
6. Reagents 7.2 UO F is radioactive, corrosive and toxic. It is a yellow
2 2
solid very soluble in H O. When heated to decomposition,
6.1 Purity of Reagents—Reagent grade chemicals shall be
above 300°C, it emits toxic fluoride fumes.
used in all tests. Unless otherwise indicated, it is intended that
all reagents conform to the specifications of the Committee on 7.3 Hydrofluoric acid is a highly corrosive acid that can
Analytical Reagents of the American Chemical Society where
severely burn skin, eyes, and mucous membranes. Hydroflu-
such specifications are available. Other grades of reagents oric acid differs from other acids because the fluoride ion
may be used, provided it is first ascertained that the reagent is
readily penetrates the skin, causing destruction of deep tissue
of sufficient high purity to permit its use without lessening the layers. Unlike other acids that are rapidly neutralized, hydro-
accuracy of the determination.
fluoric acid reactions with tissue may continue for days if left
7 untreated.FamiliarizationandcompliancewiththeSafetyData
6.2 Alumina Pellets Specification —Aluminum oxide type
Sheet is essential.
gamma has been succesfully demonstrated. These pellets are
cylinders of typically 3 mm of diameter and 5-6 mm of length,
7.4 When released to atmosphere, gaseous UF reacts with
with density of 0.39 g/cm and a total pore volume of 1.14
moisture to produce HF gas and UO F particulates.This latter
2 2
3 2
cm /g. The specific surface area is around 250 m /g measured
becomes readily visible as a white cloud. The corrosive nature
by the BET Method. The alumina pellets must have low levels
of UF , HF and UO F can result in skin burns and lung
6 2 2
of impurities, especially U, to prevent systematic bias in the
impairment. Medical evaluation is mandatory after contact
measured isotopic composition. It is strongly recommended to
with these compounds. When water-soluble UO F is inhaled
2 2
dry the alumina pellets to 120°C before use. Then, keep it in a
or ingested in large quantities it can be toxic to the kidneys.
desiccator until it reaches room temperature. Following
...

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