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ASTM C809-13

(Test Method)

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and AluminumOxide-Boron Carbide Composite Pellets

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and Aluminum<brk/>Oxide-Boron Carbide Composite Pellets

SIGNIFICANCE AND USE
3.1 Aluminum oxide pellets are used in a reactor core as filler or spacers within fuel, burnable poison, or control rods. In order to be suitable for this purpose, the material must meet certain criteria for impurity content. These test methods are designed to show whether or not a given material meets the specifications for these items as described in Specification C785.  
3.1.1 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded.  
3.2 Aluminum oxide-boron carbide composite pellets are used in a reactor core as a component in neutron absorber rods. In order to be suitable for this purpose, the material must meet certain criteria for boron content, isotopic composition, and impurity content as described in Specification C784.  
3.2.1 The material is assayed for boron to determine whether the boron content is as specified by the purchaser.  
3.2.2 Determination of the isotopic content of the boron is made to establish whether the 10B concentration is in compliance with the purchaser's specifications.  
3.2.3 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded.
SCOPE
1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade aluminum oxide and aluminum oxide-boron carbide composite pellets to determine compliance with specifications.  
1.2 The analytical procedures appear in the following order:    
Sections  
Boron by Titrimetry and ICP OES  
7 to 16  
Separation of Boron for Mass Spectrometry  
17 to 22  
Isotopic Composition by Mass Spectrometry  
23 to 26  
Separation of Halides by Pyrohydrolysis  
27 to 30  
Chloride and Fluoride by Ion-Selective Electrode  
31 to 33  
Chloride, Bromide, and Iodide by Amperometric Microtitrimetry  
34 to 36  
Trace Elements by Emission Spectroscopy  
37 to 49  
Keywords  
50
1.3 The values stated in SI units are to be regarded as the 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 precautionary statements, see Section 5.)

General Information

Status
Historical
Publication Date
31-Dec-2012
ICS
27.120.30 - Fissile materials and nuclear fuel technology
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.03 - Neutron Absorber Materials Specifications
Current Stage
Ref Project

Relations

Replaces
ASTM C809-94(2007) - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and Aluminum<br> Oxide-Boron Carbide Composite Pellets
Effective Date
01-Jan-2013
Replaced By
ASTM C809-19 - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and Aluminum<brk/>Oxide-Boron Carbide Composite Pellets
Effective Date
01-Feb-2019
Referred By
ASTM C1031-11(2022) - Standard Specification for Nuclear-Grade Aluminum Oxide Powder
Effective Date
01-Jan-2013
Referred By
ASTM C785-08(2022) - Standard Specification for Nuclear-Grade Aluminum Oxide Pellets
Effective Date
01-Jan-2013
Referred By
ASTM C784-20 - Standard Specification for Nuclear-Grade Aluminum Oxide-Boron Carbide Composite Pellets
Effective Date
01-Jan-2013
Referred By
ASTM E1652-21 - Standard Specification for Magnesium Oxide and Aluminum Oxide Powder and Crushable Insulators Used in the Manufacture of Base Metal Thermocouples, Metal-Sheathed Platinum Resistance Thermometers, and Noble Metal Thermocouples
Effective Date
01-Jan-2013

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ASTM C809-13 - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and Aluminum<brk/>Oxide-Boron Carbide Composite PelletsASTM C809-13 - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and Aluminum<brk/>Oxide-Boron Carbide Composite Pellets
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ASTM C809-13 - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and Aluminum<brk/>Oxide-Boron Carbide Composite Pellets
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REDLINE ASTM C809-13 - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and Aluminum<brk/>Oxide-Boron Carbide Composite PelletsREDLINE ASTM C809-13 - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and Aluminum<brk/>Oxide-Boron Carbide Composite Pellets
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REDLINE ASTM C809-13 - Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and Aluminum<brk/>Oxide-Boron Carbide Composite Pellets
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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: C809 − 13
Standard Test Methods for
Chemical, Mass Spectrometric, and Spectrochemical
Analysis of Nuclear-Grade Aluminum Oxide and Aluminum
1
Oxide-Boron Carbide Composite Pellets
This standard is issued under the fixed designation C809; 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 Spectrochemical Analysis of Nuclear-Grade Boron Car-
bide
1.1 These test methods cover procedures for the chemical,
C799Test Methods for Chemical, Mass Spectrometric,
mass spectrometric, and spectrochemical analysis of nuclear-
Spectrochemical,Nuclear,andRadiochemicalAnalysisof
grade aluminum oxide and aluminum oxide-boron carbide
Nuclear-Grade Uranyl Nitrate Solutions
composite pellets to determine compliance with specifications.
D1193Specification for Reagent Water
1.2 Theanalyticalproceduresappearinthefollowingorder:
E115Practice for Photographic Processing in Optical Emis-
3
Sections
sion Spectrographic Analysis (Withdrawn 2002)
E116Practice for Photographic Photometry in Spectro-
Boron by Titrimetry and ICP OES 7 to 16
3
Separation of Boron for Mass Spectrometry 17 to 22
chemical Analysis (Withdrawn 2002)
Isotopic Composition by Mass Spectrometry 23 to 26
Separation of Halides by Pyrohydrolysis 27 to 30
3. Significance and Use
Chloride and Fluoride by Ion-Selective Electrode 31 to 33
Chloride, Bromide, and Iodide byAmperometric Microtitrimetry 34 to 36
Trace Elements by Emission Spectroscopy 37 to 49 3.1 Aluminum oxide pellets are used in a reactor core as
Keywords 50
fillerorspacerswithinfuel,burnablepoison,orcontrolrods.In
1.3 The values stated in SI units are to be regarded as the order to be suitable for this purpose, the material must meet
standard.
certain criteria for impurity content. These test methods are
designed to show whether or not a given material meets the
1.4 This standard does not purport to address all of the
specifications for these items as described in Specification
safety concerns, if any, associated with its use. It is the
C785.
responsibility of the user of this standard to establish appro-
priate safety and health practices and determine the applica- 3.1.1 Impurity content is determined to ensure that the
bility of regulatory limitations prior to use. (For specific
maximum concentration limit of certain impurity elements is
precautionary statements, see Section 5.)
not exceeded.
3.2 Aluminum oxide-boron carbide composite pellets are
2. Referenced Documents
usedinareactorcoreasacomponentinneutronabsorberrods.
2
2.1 ASTM Standards:
In order to be suitable for this purpose, the material must meet
C784Specification for Nuclear-Grade Aluminum Oxide-
certain criteria for boron content, isotopic composition, and
Boron Carbide Composite Pellets
impurity content as described in Specification C784.
C785SpecificationforNuclear-GradeAluminumOxidePel-
3.2.1 The material is assayed for boron to determine
lets
whether the boron content is as specified by the purchaser.
C791Test Methods for Chemical, Mass Spectrometric, and
3.2.2 Determination of the isotopic content of the boron is
10
made to establish whether the B concentration is in compli-
ance with the purchaser’s specifications.
1
These test methods are under the jurisdiction of ASTM Committee C26 on
Nuclear Fuel Cycle and are the direct responsibility of Subcommittee C26.03 on
3.2.3 Impurity content is determined to ensure that the
Neutron Absorber Materials Specifications.
maximum concentration limit of certain impurity elements is
Current edition approved Jan. 1, 2013. Published January 2013. Originally
not exceeded.
approved in 1980. Last previous edition approved in 2007 as C809–94(2007).
DOI: 10.1520/C0809-13.
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
3
Standards volume information, refer to the standard’s Document Summary page on The last approved version of this historical standard is referenced on
the ASTM website. www.astm.org.
Copyright ©ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA19428-2959. United States
1

---------------------- Page: 1 ----------------------
C809 − 13
4. Reagents trations of Fe<2%,Ti<1%. Interferences by dissolved CO
2
shall be removed by heating the sample solution or by purging
4.1 Purity of Reagents—Reagent grade chemicals shall be
the sample solution with nitrogen.
used in all tests. Unless otherwise indicated, it is intended that
all reagents shall conform to the specifications of the Commit- 9.2 ICP OES—Interference effects depend primarily upon
tee onAnalytical
...

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: C809 − 94 (Reapproved 2007) C809 − 13
Standard Test Methods for
Chemical, Mass Spectrometric, and Spectrochemical
Analysis of Nuclear-Grade Aluminum Oxide and Aluminum
1
Oxide-Boron Carbide Composite Pellets
This standard is issued under the fixed designation C809; 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 test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade
aluminum oxide and aluminum oxide-boron carbide composite pellets to determine compliance with specifications.
1.2 The analytical procedures appear in the following order:
Sections
Boron by Titrimetry 7 to 13
Boron by Titrimetry and ICP OES 7 to 16
Separation of Boron for Mass Spectrometry 14 to 19
Separation of Boron for Mass Spectrometry 17 to 22
Isotopic Composition by Mass Spectrometry 20 to 23
Isotopic Composition by Mass Spectrometry 23 to 26
Separation of Halides by Pyrohydrolysis 24 to 27
Separation of Halides by Pyrohydrolysis 27 to 30
Fluoride by Ion-Selective Electrode 28 to 30
Chloride and Fluoride by Ion-Selective Electrode 31 to 33
Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 31 to 33
Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 34 to 36
Trace Elements by Emission Spectroscopy 34 to 46
Trace Elements by Emission Spectroscopy 37 to 49
Keywords 50
1.3 The values stated in SI units are to be regarded as the 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 precautionary statements, see Section 5.)
2. Referenced Documents
2
2.1 ASTM Standards:
C784 Specification for Nuclear-Grade Aluminum Oxide-Boron Carbide Composite Pellets
C785 Specification for Nuclear-Grade Aluminum Oxide Pellets
C791 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Boron Carbide
C799 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-
Grade Uranyl Nitrate Solutions
D1193 Specification for Reagent Water
3
E115 Practice for Photographic Processing in Optical Emission Spectrographic Analysis (Withdrawn 2002)
3
E116 Practice for Photographic Photometry in Spectrochemical Analysis (Withdrawn 2002)
1
These test methods are under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and are the direct responsibility of Subcommittee C26.03 on Neutron
Absorber Materials Specifications.
Current edition approved July 1, 2007Jan. 1, 2013. Published August 2007January 2013. Originally approved in 1980. Last previous edition approved in 20002007 as
C809 – 94 (2000).(2007). DOI: 10.1520/C0809-94R07.10.1520/C0809-13.
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.
3
The last approved version of this historical standard is referenced on www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C809 − 13
3. Significance and Use
3.1 Aluminum oxide pellets are used in a reactor core as filler or spacers within fuel, burnable poison, or control rods. In order
to be suitable for this purpose, the material must meet certain criteria for impurity content. These test methods are designed to show
whether or not a given material meets the specifications for these items as described in Specification C785.
3.1.1 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not
exceeded.
3.2 Aluminum oxide-boron carbide composite pellets are used in a reactor core as a component in neutron absorber rods. In
order to be suitable for this purpose, the material must meet certain criteria for boron content, isotopic composition, and impurity
content as described in Specification C784.
3.2.1 The material is assayed for boron to determine whether the boron content is as
...

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ASTM C1268-23(Test Method)
Standard Test Method for Quantitative Determination of 241Am in Plutonium by Gamma-Ray Spectrometry

SIGNIFICANCE AND USE
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Section  
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16  
9  
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17  
10  
Open-Vessel (with Reflux Condenser) Dissolution of Mixed Oxide Pellets  
18  
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ABSTRACT
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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