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ASTM C889-11

(Test Method)

Standard Test Methods for Chemical and Mass Spectrometric Analysis of Nuclear-Grade Gadolinium Oxide (Gd2O3) Powder

Standard Test Methods for Chemical and Mass Spectrometric Analysis of Nuclear-Grade Gadolinium Oxide (Gd<sub>2</sub>O<sub>3</sub>) Powder

SIGNIFICANCE AND USE
Gadolinium oxide powder is used, with subsequent processing, in nuclear fuel applications, such as an addition to uranium dioxide. These test methods are designed to determine whether the material meets the requirements described in Specification C888.
The material is analyzed to determine whether it contains the minimum gadolinium oxide content specified.
The loss on ignition and impurity content are determined to ensure that the weight loss and the maximum concentration limit of specified impurity elements are not exceeded.
SCOPE
1.1 These test methods cover procedures for the chemical and mass spectrometric analysis of nuclear-grade gadolinium oxide powders to determine compliance with specifications.
1.2 The analytical procedures appear in the following order:
Sections Carbon by Direct CombustionThermal Conductivity  C1408 Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method  Total Chlorine and Fluorine by Pyrohydrolysis Ion
Selective Electrode  C1502 Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide  Loss of Weight on Ignition7-13 Sulfur by CombustionIodometric Titration  Impurity Elements by a Spark-Source Mass Spectrographic   C761 Test Methods for Chemical, Mass Spectrometric, Spectrochemical,Nuclear, and Radiochemical Analysis of Uranium Hexafluoride  C1287 Test Method for Determination of Impurities In Uranium Dioxide By Inductively Coupled Plasma Mass Spectrometry  Gadolinium Content in Gadolinium Oxide by Impurity
Correction14-17
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.4 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 and health practices and determine the applicability of regulatory limitations prior to use. For specific hazard statements, see Section 5.  
7.1 This test method covers the loss-on-ignition of volatile constituents from nuclear-grade gadolinium oxide (Gd2O3) powder.  
14.1 The percent gadolinium oxide content of powders, exclusive of volatiles, is determined by calculation after the material has been analyzed to determine the total impurities.

General Information

Status
Historical
Publication Date
31-May-2011
ICS
27.120.30 - Fissile materials and nuclear fuel technology
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.05 - Methods of Test
Current Stage
Ref Project

Relations

Replaces
ASTM C889-06 - Standard Test Methods for Chemical and Mass Spectrometric Analysis of Nuclear-Grade Gadolinium Oxide (Gd<sub>2</sub>O<sub>3</sub>) Powder
Effective Date
01-Jun-2011
Replaced By
ASTM C889-18 - Standard Test Methods for Chemical and Mass Spectrometric Analysis of Nuclear-Grade Gadolinium Oxide (Gd<inf>2</inf>O<inf>3</inf>) Powder
Effective Date
01-Feb-2018
Referred By
ASTM F2168-13(2019) - Standard Specification for Packing Material, Graphitic, Corrugated Ribbon or Textured Tape, and Die-Formed Ring
Effective Date
01-Jun-2011
Referred By
ASTM C888-18 - Standard Specification for Nuclear-Grade Gadolinium Oxide (Gd<inf>2</inf>O<inf>3</inf >) Powder
Effective Date
01-Jun-2011
Referred By
ASTM F2191/F2191M-13(2020)e1 - Standard Specification for Packing Material, Graphitic or Carbon Braided Yarn
Effective Date
01-Jun-2011

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ASTM C889-11 - Standard Test Methods for Chemical and Mass Spectrometric Analysis of Nuclear-Grade Gadolinium Oxide (Gd<sub>2</sub>O<sub>3</sub>) PowderASTM C889-11 - Standard Test Methods for Chemical and Mass Spectrometric Analysis of Nuclear-Grade Gadolinium Oxide (Gd<sub>2</sub>O<sub>3</sub>) Powder
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REDLINE ASTM C889-11 - Standard Test Methods for Chemical and Mass Spectrometric Analysis of Nuclear-Grade Gadolinium Oxide (Gd<sub>2</sub>O<sub>3</sub>) PowderREDLINE ASTM C889-11 - Standard Test Methods for Chemical and Mass Spectrometric Analysis of Nuclear-Grade Gadolinium Oxide (Gd<sub>2</sub>O<sub>3</sub>) Powder
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REDLINE ASTM C889-11 - Standard Test Methods for Chemical and Mass Spectrometric Analysis of Nuclear-Grade Gadolinium Oxide (Gd<sub>2</sub>O<sub>3</sub>) Powder
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Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation: C889 − 11
Standard Test Methods for
Chemical and Mass Spectrometric Analysis of Nuclear-
1
Grade Gadolinium Oxide (Gd O ) Powder
2 3
This standard is issued under the fixed designation C889; 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.
This standard has been approved for use by agencies of the Department of Defense.
1. Scope bility of regulatory limitations prior to use. For specific hazard
statements, see Section 5.
1.1 These test methods cover procedures for the chemical
and mass spectrometric analysis of nuclear-grade gadolinium
2. Referenced Documents
oxide powders to determine compliance with specifications.
3
2.1 ASTM Standards:
1.2 The analytical procedures appear in the following order:
C761 Test Methods for Chemical, Mass Spectrometric,
Sections
2
Carbon by Direct Combustion—Thermal Conductivity Spectrochemical, Nuclear, and RadiochemicalAnalysis of
3
C1408 Test Method for Carbon (Total) in Uranium Oxide
Uranium Hexafluoride
Powders and Pellets By Direct Combustion-Infrared Detec-
C888 Specification for Nuclear-Grade Gadolinium Oxide
tion Method
4
Total Chlorine and Fluorine by Pyrohydrolysis Ion—
(Gd O ) Powder
2 3
Selective Electrode
5 C1287 Test Method for Determination of Impurities in
C1502 Test Method for Determination of Total Chlorine and
Fluorine in Uranium Dioxide and Gadolinium Oxide
Nuclear Grade Uranium Compounds by Inductively
Loss of Weight on Ignition 7-13
Coupled Plasma Mass Spectrometry
2
Sulfur by Combustion—Iodometric Titration
2
C1408 Test Method for Carbon (Total) in Uranium Oxide
Impurity Elements by a Spark-Source Mass Spectrographic
3
C761 Test Methods for Chemical, Mass Spectrometric,
Powders and Pellets By Direct Combustion-Infrared De-
Spectrochemical,Nuclear, and Radiochemical Analysis of
tection Method
Uranium Hexafluoride
3
C1287 Test Method for Determination of Impurities In Ura-
C1502 Test Method for Determination of Total Chlorine and
nium Dioxide By Inductively Coupled Plasma Mass Spec-
Fluorine in Uranium Dioxide and Gadolinium Oxide
trometry
Gadolinium Content in Gadolinium Oxide by Impurity 14-17 D1193 Specification for Reagent Water
Correction
1.3 The values stated in SI units are to be regarded as 3. Significance and Use
standard. No other units of measurement are included in this
3.1 Gadolinium oxide powder is used, with subsequent
standard.
processing, in nuclear fuel applications, such as an addition to
1.4 This standard does not purport to address all of the
uranium dioxide.These test methods are designed to determine
safety concerns, if any, associated with its use. It is the
whether the material meets the requirements described in
responsibility of the user of this standard to establish appro-
Specification C888.
priate safety and health practices and determine the applica-
3.1.1 The material is analyzed to determine whether it
contains the minimum gadolinium oxide content specified.
3.1.2 The loss on ignition and impurity content are deter-
1
These test methods are under the jurisdiction of ASTM Committee C26 on
mined to ensure that the weight loss and the maximum
Nuclear Fuel Cycle and are the direct responsibility of Subcommittee C26.05 on
Methods of Test. concentration limit of specified impurity elements are not
Current edition approved June 1, 2011. Published June 2011. Originally
exceeded.
approved in 1978. Last previous edition approved in 2006 as C889 – 06. DOI:
10.1520/C0889-11.
2
Discontinued January 1999. See C889–90. 4. Reagents
3
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 4.1 Purity of Reagents—Reagent grade chemicals shall be
Standards volume information, refer to the standard’s Document Summary page on
used in all tests. Unless otherwise indicated, it is intended that
the ASTM website.
4 all reagents shall conform to the specifications of the Commit-
Discontinued March 2005. See C1408.
5
Discontinued March 2005. See C889–90. tee onAnalytical Reagents of theAmerican Chemical Society,
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C889 − 11
6
where such specifications are available. Other grades may be 10. Reagent
used, provided it is first ascertained that the reagent is of
10.1 Drying Desiccant.
sufficiently high purity to permit its use without lessening the
accuracy of the determination.
11. Procedure
4.2 Purity of Water—Unless otherwise indicated, references
11.1 Heat the furnace to 925 6 25°C.
...

This document is not anASTM standard and is intended only to provide the user of anASTM 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:C889–06 Designation:C889–11
Standard Test Methods for
Chemical and Mass Spectrometric Analysis of Nuclear-
1
Grade Gadolinium Oxide (Gd O ) Powder
2 3
This standard is issued under the fixed designation C889; 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.
This standard has been approved for use by agencies of the Department of Defense.
1. Scope
1.1 These test methods cover procedures for the chemical and mass spectrometric analysis of nuclear-grade gadolinium oxide
powders to determine compliance with specifications.
1.2 The analytical procedures appear in the following order:
Sections
2
Carbon by Direct Combustion—Thermal Conductivity
3
C1408 Test Method for Carbon (Total) in Uranium Oxide
Powders and Pellets By Direct Combustion-Infrared Detec-
tion Method
4
Total Chlorine and Fluorine by Pyrohydrolysis Ion—
Selective Electrode
5
C1502 Test Method for Determination of Total Chlorine and
Fluorine in Uranium Dioxide and Gadolinium Oxide
Loss of Weight on Ignition 7-13
2
Sulfur by Combustion—Iodometric Titration
2
Impurity Elements by a Spark-Source Mass Spectrographic
3
C761 Test Methods for Chemical, Mass Spectrometric, Spec-
trochemical,Nuclear, and Radiochemical Analysis of Uranium
Hexafluoride
3
C1287 Test Method for Determination of Impurities In Ura-
nium Dioxide By Inductively Coupled Plasma Mass Spec-
trometry
Gadolinium Content in Gadolinium Oxide by Impurity 14-17 C1502 Test
Correction Method for Deter-
mination of Total
Chlorine and
Fluorine in Ura-
nium Dioxide and
Gadolinium Oxide
1.3
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.4 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 and health practices and determine the applicability of regulatory
limitations prior to use. For specific hazard statements, see Section 5.
2. Referenced Documents
3
2.1 ASTM Standards:
C761 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium
Hexafluoride
C888 Specification for Nuclear-Grade Gadolinium Oxide (Gd O ) Powder
2 3
1
These test methods 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 Jan.June 1, 2006.2011. Published February 2006.June 2011. Originally approved in 1978. Last previous edition approved in 19992006 as
C889–99.C889 – 06. DOI: 10.1520/C0889-06.10.1520/C0889-11.
2
Discontinued January 1999. See C889–90.
3
For referencedASTM standards, visit theASTM website, www.astm.org, or contactASTM 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.
4
Discontinued March 2005. See C1408.
5
Discontinued March 2005. See C889–90.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
C889–11
C1287 Test Method for Determination of Impurities in Nuclear Grade Uranium Compounds by Inductively Coupled Plasma
Mass Spectrometry
C1408 Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection
Method
C1502 Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide
D1193 Specification for Reagent Water
3. Significance and Use
3.1 Gadolinium oxide powder is used, with subsequent processing, in nuclear fuel applications, such as an addition to uranium
dioxide. These test methods are designed to determine whether the material meets the requirements described in Specification
C888.
3.1.1 The material is analyzed to determine whether it contains the minimum gadolinium oxide content specified.
3.1.2 The loss on ignition and impurity content are determined to ensure that the weight loss and the maximum concentration
limit of specified impurity elements are not exceeded.
4. Reagents
4.1 Purity of Reagents—Reagent grade chemicals shall be used in all tests. Unless otherwise indicated, it is intended that all
reagents shall conform to th
...

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10  
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18  
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This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. The diversity of manufacturing methods shall be recognized by which uranium-plutonium dioxide pellets are produced and the many special requirements for chemical and physical characterization that may be imposed by the operating conditions to which the pellets will be subjected in specific reactor systems. The following are different chemical requirements that shall be determined: uranium content, plutonium content, impurity content, stoichiometry, moisture content, gas content, and americium-241 content. Nuclear requirements such as isotopic content, plutonium equivalent at a given date, equivalent boron content, and reactivity shall also be determined. Physical properties of the pellets like dimensions, density, grain size, pore morphology, plutonium-oxide homogeneity, plutonium-oxide particle size, plutonium-oxide particle distribution, integrity, and surface cracks shall be determined as well. The surfaces of finished pellets shall be visually free of loose chips, oil, macroscopic inclusions, and foreign materials. An estimate of the fuel pellet irradiation stability shall be obtained unless adequate allowance for such effects are factored into the fuel rod design. The estimate of the stability shall consist of either conformance to the thermal stability test as specified in the or by adequate correlation of manufacturing process or microstructure to in-reactor behavior, or both.
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SCOPE
1.1 This terminology standard contains terms, definitions, descriptions of terms, nomenclature, and explanations of acronyms and symbols specifically associated with standards under the jurisdiction of Committee C26 on Nuclear Fuel Cycle. The content of this terminology standard may also be applicable to documents not under the jurisdiction of Committee C26, in which case this terminology standard may be referenced in those documents.  
1.2 While subcommittees within Committee C26 are free to only provide terms and definitions within individual standards, each subcommittee may request the addition of utilized terms and definitions to this terminology standard if it believes that such serves the broader interest of Committee C26 and the nuclear fuel cycle profession. Therefore, terms and definitions proposed for inclusion in Terminology C859 need not be used in more than one committee standard before being considered.  
1.3 In general, technical terms that are defined in common dictionaries would not also be defined in this terminology standard unless there is a need to emphasize a specific definition in making appropriate use of a Committee C26 standard.  
1.4 Subcommittee C26.10 (Nondestructive Assay) also has a terminology standard applicable to its standards: Terminology C1673.  
1.5 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.

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ASTM
ASTM C1554-18(2023)(Guide)
Standard Guide for Materials Handling Equipment for Hot Cells

SIGNIFICANCE AND USE
4.1 Materials handling equipment operability and long-term integrity are concerns that originate during the design and fabrication sequences. Such concerns are most efficiently addressed during one or the other of these stages. Equipment operability and integrity can be compromised during handling and installation sequences. For this reason, the subject equipment should be handled and installed under closely controlled and supervised conditions.  
4.2 This guide is intended as a supplement to other standards (Section 2, Referenced Documents), and to federal and state regulations, codes, and criteria applicable to the design of equipment intended for this use.  
4.3 This guide is intended to be generic and to apply to a wide range of types and configurations of materials handling equipment.  
4.4 The term materials handling equipment is used herein in a generic sense. It includes manipulators, cranes, carts or bogies, and special equipment for handling tools and material in hot cells.  
4.5 This service imposes stringent requirements on the quality and the integrity of the equipment, as follows:  
4.5.1 Boots and similar protective covers should not restrict movement of the equipment, should be properly sealed to the equipment and should withstand the radiation, cell atmosphere, dust, cell temperatures, chemical exposures, and cleaning and decontamination reagents, and also resist snags and tearing.  
4.5.2 Materials handling equipment should be capable of withstanding rigorous chemical cleaning and decontamination procedures.  
4.5.3 Materials handling equipment should be designed and fabricated to remain dimensionally stable throughout its life cycle.  
4.5.4 Attention to fabrication tolerances is necessary to allow the proper fit-up between components for the proper installation and mounting of materials handling equipment in hot cells, for example, when parts or components are being replaced. Fabrication tolerances should be controlled to provide sufficie...
SCOPE
1.1 Intent:  
1.1.1 This guide covers materials handling equipment used in hot cells (shielded cells) for the processing and handling of nuclear and radioactive materials. The intent of this guide is to aid in the selection and design of materials handling equipment for hot cells in order to minimize equipment failures and maximize the equipment utility.  
1.1.2 It is intended that this guide record the principles and caveats that experience has shown to be essential to the design, fabrication, installation, maintenance, repair, replacement, and decontamination and decommissioning of materials handling equipment capable of meeting the stringent demands of operating, dependably and safely, in a hot cell environment where operator visibility is limited due to the radiation exposure hazards.  
1.1.3 This guide may apply to materials handling equipment in other radioactive remotely operated facilities such as suited entry repair areas and canyons, but does not apply to materials handling equipment used in commercial power reactors.  
1.1.4 This guide covers mechanical master-slave manipulators and electro-mechanical manipulators, but does not cover electro-hydraulic manipulators.  
1.2 Applicability:  
1.2.1 This guide is intended to be applicable to equipment used under one or more of the following conditions:
1.2.1.1 The materials handled or processed constitute a significant radiation hazard to man or to the environment.
1.2.1.2 The equipment will generally be used over a long-term life cycle (for example, in excess of two years), but equipment intended for use over a shorter life cycle is not excluded.
1.2.1.3 The equipment can neither be accessed directly for purposes of operation or maintenance, nor can the equipment be viewed directly, for example, without shielded viewing windows, periscopes, or a video monitoring system.  
1.3 User Caveats:  
1.3.1 This standard is not a substitute for applied engin...

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ASTM
ASTM C1703-18(2023)(Practice)
Standard Practice for Sampling of Gaseous Uranium Hexafluoride for Enrichment

SIGNIFICANCE AND USE
5.1 Uranium hexafluoride is normally produced and handled in large (typically 1 to 14-ton) quantities and must, therefore, be characterized by reference to representative samples (see ISO 7195). The samples are used to determine compliance with the applicable commercial specification C787. The quantities involved, physical properties, chemical reactivity, and hazardous nature of UF6 are such that for representative sampling, specially designed equipment must be used and operated in accordance with the most carefully controlled and stringent procedures. This practice can be used by UF6 converters to review the effectiveness of existing procedures or as a guide to the design of equipment and procedures for future use.  
5.2 The intention of this practice is to avoid liquid UF6 sampling once the cylinder has been filled. For safety reasons, manipulation of large quantities of liquid UF6 should be avoided when possible.  
5.3 It is emphasized that this practice is not meant to address conventional or nuclear criticality safety issues.
SCOPE
1.1 This practice covers methods for withdrawing representative sample(s) of uranium hexafluoride (UF6) during a transfer occurring in the gas phase. Such transfer in the gas phase can take place during the filling of a cylinder during a continuous production process, for example the distillation column in a conversion facility. Such sample(s) may be used for determining compliance with the applicable commercial specification, for example Specification C787.  
1.2 Since UF6 sampling is taken during the filling process, this practice does not address any special additional arrangements that may be agreed upon between the buyer and the seller when the sampled bulk material is being added to residues already present in a container (“heels recycle”). Such arrangements will be based on QA procedures such as traceability of cylinder origin (to prevent for example contamination with irradiated material).  
1.3 If the receiving cylinder is purged after filling and sampling, special verifications must be performed by the user to verify the representativity of the sample(s). It is then expected that the results found on volatile impurities with gas phase sampling may be conservative.  
1.4 This practice is only applicable when the transfer occurs in the gas phase. When the transfer is performed in the liquid phase, Practice C1052 should apply. This practice does not apply to gas sampling after the cylinder has been filled since the sample taken will not be representative of the cylinder.  
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.

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ASTM
ASTM C1347-08(2023)(Practice)
Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis

SIGNIFICANCE AND USE
4.1 The materials covered that must meet ASTM specifications are uranium metal and uranium oxide.  
4.2 Uranium materials are used as nuclear reactor fuel. For this use, these materials must meet certain criteria for uranium content, uranium-235 enrichment, and impurity content, as described in Specifications C753 and C776. The material is assayed for uranium to determine whether the content is as specified.  
4.3 Uranium alloys, refractory uranium materials, and uranium containing scrap and ash are unique uranium materials for which the user must determine the applicability of this practice. In general, these unique uranium materials are dissolved with various acid mixtures or by fusion with various fluxes.
SCOPE
1.1 This practice covers dissolution treatments for uranium materials that are applicable to the test methods used for characterizing these materials for uranium elemental, isotopic, and impurities determinations. Dissolution treatments for the major uranium materials assayed for uranium or analyzed for other components are listed.  
1.2 The treatments, in order of presentation, are as follows:    
Procedure Title  
Section  
Dissolution of Uranium Metal and Oxide with Nitric Acid  
8.1  
Dissolution of Uranium Oxides with Nitric Acid and Residue
Treatment  
8.2  
Dissolution of Uranium-Aluminum Alloys in Hydrochloric Acid
with Residue Treatment  
8.3  
Dissolution of Uranium Scrap and Ash by Leaching with Nitric
Acid and Treatment of Residue by Carbonate Fusion  
8.4  
Dissolution of Refractory Uranium-Containing Material by
Carbonate Fusion  
8.5  
Dissolution of Uranium—Aluminum Alloys
Uranium Scrap and Ash, and Refractory
Uranium-Containing Materials by
Microwave Treatment  
8.6  
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.4 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 hazards statements are given in Section 7.  
1.5 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.

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ASTM
ASTM C1165-23(Test Method)
Standard Test Method for Determining Plutonium by Controlled-Potential Coulometry in H2SO4 at a Platinum Working Electrode

SIGNIFICANCE AND USE
5.1 This test method is used to ascertain whether or not materials meet specifications for plutonium concentration or plutonium mass fraction.  
5.1.1 The materials (nuclear grade plutonium nitrate solutions, plutonium metal, plutonium oxide powder, and mixed oxide and carbide powders and pellets) to which this test method applies are subject to nuclear safeguards regulations governing their possession and use. However, adherence to this test method does not automatically guarantee regulatory acceptance of the resulting safeguards measurements. It remains the sole responsibility of the user of this test method to ensure that its application to safeguards has the approval of the proper regulatory authorities.  
5.1.2 When used in conjunction with appropriate certified reference materials (CRMs), this test method can demonstrate traceability to the international measurements system (SI).  
5.2 Fitness for Purpose of Safeguards and Nuclear Safety Application—Methods intended for use in safeguards and nuclear safety applications shall meet the requirements specified by Guide C1068 for use in such applications.  
5.3 A chemical calibration of the coulometer is necessary for accurate results.
FIG. 1 Example of a Cell Design Used at Los Alamos National Laboratory (LANL)
SCOPE
1.1 This test method covers the determination of milligram quantities of plutonium in unirradiated uranium-plutonium mixed oxide having a U/Pu ratio range of 0.1 to 10. This test method is also applicable to plutonium metal, plutonium oxide, uranium-plutonium mixed carbide, various plutonium compounds including fluoride and chloride salts, and plutonium solutions.  
1.2 The recommended amount of plutonium for each aliquant in the coulometric analysis is 5 mg to 10 mg. Precision worsens for lower amounts of plutonium, and elapsed time of electrolysis becomes impractical for higher amounts of plutonium.  
1.3 The quantity values stated in SI units are to be regarded as standard. The quantity values with non-SI units are given in parentheses for information only.  
1.4 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 Section 9.  
1.5 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.

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