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ASTM C968-12

(Test Method)

Standard Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets

Standard Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets

SIGNIFICANCE AND USE
The test methods in this method are designed to show whether a given material is in accordance with Specification C922.
SCOPE
1.1 These test methods cover procedures for the analysis of sintered gadolinium oxide-uranium dioxide pellets to determine compliance with specifications.
1.2 The analytical procedures appear in the following order: Section Carbon (Total) by Direct CombustionThermal Conductivity Method  C1408 Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection Method  Chlorine and Fluorine by Pyrohydrolysis Ion-Selective Electrode Method  C1502 Test Method for Determination of Total Chlorine and Fluorine in Uranium Dioxide and Gadolinium Oxide  Gadolinia Content by Energy-Dispersive X-Ray Spectrometry  C1456 Test Method for Determination of Uranium or Gadolinium, or Both, in Gadolinium Oxide-Uranium Oxide Pellets or by X-Ray Fluorescence (XRF)  Hydrogen by Inert Gas Fusion  C1457 Test Method for Determination of Total Hydrogen Content of Uranium Oxide Powders and Pellets by Carrier Gas Extraction  Isotopic Uranium Composition by Multiple-Filament Surface-Ionization Mass Spectrometric Method  C1413 Test Method for Isotopic Analysis of Hydrolysed Uranium Hexafluoride And Uranyl Nitrate Solutions By Thermal Ionization Mass Spectrometry  C1347 Practice for Preparation and Dissolution of Uranium Materials for Analysis  Nitrogen by DistillationNessler Reagent (Photometric) Method6 to 16 Oxygen-to-Metal Ratio of Sintered Gadolinium Oxide-Uranium Dioxide Pellets  C1430 Test Method for Determination of Uranium, Oxygen to Uranium, and Oxygen to Metal (O/M) in Sintered Uranium Dioxide and Gadolinia-Uranium Dioxide Pellets by Atmospheric Equilibration  Spectrochemical Determination of Trace Impurity Elements  C1517 Test Method for Determination of Metallic Impurities in Uranium Metal or Compounds by DC-Arc Emission Spectroscopy  Total Gas by Hot Vacuum Extraction  Ceramographic Determination of Free Gd2O3 and Free UO2 to Estimate the Homogeneity of (U,Gd)O2 Pellets17 to 24 Ceramographic Determination of Average Grain Size by Linear Intercept after Chemical Etching 25 to 32
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.

General Information

Status
Historical
Publication Date
31-Dec-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 C968-06 - Standard Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets
Effective Date
01-Jan-2012
Replaced By
ASTM C968-19 - Standard Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets
Effective Date
01-Sep-2019
Referred By
ASTM C1430-18 - Standard Test Method for Determination of Uranium, Oxygen to Uranium (O/U), and Oxygen to Metal (O/M) in Sintered Uranium Dioxide and Gadolinia-Uranium Dioxide Pellets by Atmospheric Equilibration
Effective Date
01-Jan-2012
Referred By
ASTM C922-21 - Standard Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets for Light Water Reactors
Effective Date
01-Jan-2012

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ASTM C968-12 - Standard Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide PelletsASTM C968-12 - Standard Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide 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: C968 − 12
Standard Test Methods for
Analysis of Sintered Gadolinium Oxide-Uranium Dioxide
1
Pellets
This standard is issued under the fixed designation C968; 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
Section
Ceramographic Determination of Free Gd O and Free UO to 17 to 24
2 3 2
1.1 These test methods cover procedures for the analysis of
Estimate the Homogeneity of (U,Gd)O Pellets
2
sintered gadolinium oxide-uranium dioxide pellets to deter- Ceramographic Determination of Average Grain Size by Linear 25 to 32
Intercept after Chemical Etching
mine compliance with specifications.
1.3 The values stated in SI units are to be regarded as the
1.2 Theanalyticalproceduresappearinthefollowingorder:
standard.
Section
2
1.4 This standard does not purport to address all of the
Carbon (Total) by Direct Combustion—Thermal Conductivity Method
3
C1408 Test Method for Carbon (Total) in Uranium Oxide Powders
safety concerns, if any, associated with its use. It is the
and Pellets By Direct Combustion-Infrared Detection Method
responsibility of the user of this standard to establish appro-
4
Chlorine and Fluorine by Pyrohydrolysis Ion-Selective Electrode
priate safety and health practices and determine the applica-
Method
3
C1502 Test Method for Determination of Total Chlorine and Fluorine
bility of regulatory limitations prior to use.
in Uranium Dioxide and Gadolinium Oxide
4
Gadolinia Content by Energy-Dispersive X-Ray Spectrometry
2. Referenced Documents
3
C1456 Test Method for Determination of Uranium or Gadolinium, or
3
Both, in Gadolinium Oxide-Uranium Oxide Pellets or by X-Ray 2.1 ASTM Standards:
Fluorescence (XRF)
C922SpecificationforSinteredGadoliniumOxide-Uranium
4
Hydrogen by Inert Gas Fusion
3
Dioxide Pellets
C1457 Test Method for Determination of Total Hydrogen Content of
Uranium Oxide Powders and Pellets by Carrier Gas Extraction C1347Practice for Preparation and Dissolution of Uranium
2
Isotopic Uranium Composition by Multiple-Filament Surface-
Materials for Analysis
Ionization Mass Spectrometric Method
3 C1408Test Method for Carbon (Total) in Uranium Oxide
C1413 Test Method for Isotopic Analysis of Hydrolysed Uranium
Hexafluoride And Uranyl Nitrate Solutions By Thermal Ionization
Powders and Pellets By Direct Combustion-Infrared De-
Mass Spectrometry
tection Method
3
C1347 Practice for Preparation and Dissolution of Uranium Materials
C1413Test Method for Isotopic Analysis of Hydrolyzed
for Analysis
Nitrogen by Distillation—Nessler Reagent (Photometric) Method 6 to 16
Uranium Hexafluoride and Uranyl Nitrate Solutions by
4
Oxygen-to-Metal Ratio of Sintered Gadolinium Oxide-Uranium Diox-
Thermal Ionization Mass Spectrometry
ide Pellets
3
C1430Test Method for Determination of Uranium, Oxygen
C1430 Test Method for Determination of Uranium, Oxygen to
Uranium, and Oxygen to Metal (O/M) in Sintered Uranium Dioxide
to Uranium (O/U), and Oxygen to Metal (O/M) in
and Gadolinia-Uranium Dioxide Pellets by Atmospheric Equilibra-
Sintered Uranium Dioxide and Gadolinia-Uranium Diox-
tion
4
Spectrochemical Determination of Trace Impurity Elements ide Pellets by Atmospheric Equilibration
3
C1517 Test Method for Determination of Metallic Impurities in Ura-
C1456Test Method for Determination of Uranium or Gado-
nium Metal or Compounds by DC-Arc Emission Spectroscopy
linium (or both) in Gadolinium Oxide-Uranium Oxide
2
Total Gas by Hot Vacuum Extraction
Pellets or by X-Ray Fluorescence (XRF)
C1457Test Method for Determination of Total Hydrogen
1
ContentofUraniumOxidePowdersandPelletsbyCarrier
These test methods are under the jurisdiction of ASTM C26 on Nuclear Fuel
Cycle and are the direct responsibility of C26.05 on Methods of Test. Gas Extraction
Current edition approved Jan. 1, 2012. Published February 2012. Originally
C1502TestMethodforDeterminationofTotalChlorineand
approved in 1981. Last previous edition approved in 2006 as C968–06. DOI:
Fluorine in Uranium Dioxide and Gadolinium Oxide
10.1520/C0968-12.
2
C1517TestMethodforDeterminationofMetallicImpurities
Discontinued 1999. See C968–94.
3
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
in Uranium Metal or Compounds by DC-Arc Emission
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Spectroscopy
Standards volume information, refer to the standard’s Document Summary page on
D1193Specification for Reagent Water
the ASTM website.
4
Discontinued 2005. See C968–99. E112Test Methods for Determining Average Grain Size
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA
...

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:C968–06 Designation:C968–12
Standard Test Methods for
Analysis of Sintered Gadolinium Oxide-Uranium Dioxide
1
Pellets
This standard is issued under the fixed designation C968; 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 analysis of sintered gadolinium oxide-uranium dioxide pellets to determine
compliance with specifications.
1.2 The analytical procedures appear in the following order:
Section
2
Carbon (Total) by Direct Combustion—Thermal Conductivity Method
3
C1408 Test Method for Carbon (Total) in Uranium Oxide Powders
and Pellets By Direct Combustion-Infrared Detection Method
4
Chlorine and Fluorine by Pyrohydrolysis Ion-Selective Electrode
Method
3
C1502 Test Method for Determination of Total Chlorine and Fluorine
in Uranium Dioxide and Gadolinium Oxide
4
Gadolinia Content by Energy-Dispersive X-Ray Spectrometry
3
C1456 Test Method for Determination of Uranium or Gadolinium, or
Both, in Gadolinium Oxide-Uranium Oxide Pellets or by X-Ray
Fluorescence (XRF)
4
Hydrogen by Inert Gas Fusion
3
C1457 Test Method for Determination of Total Hydrogen Content of
Uranium Oxide Powders and Pellets by Carrier Gas Extraction
2
Isotopic Uranium Composition by Multiple-Filament Surface-
Ionization Mass Spectrometric Method
3
C1413 Test Method for Isotopic Analysis of Hydrolysed Uranium
Hexafluoride And Uranyl Nitrate Solutions By Thermal Ionization
Mass Spectrometry
3
C1347 Practice for Preparation and Dissolution of Uranium Materials
for Analysis
Nitrogen by Distillation—Nessler Reagent (Photometric) Method 6 to 16
4
Oxygen-to-Metal Ratio of Sintered Gadolinium Oxide-Uranium Diox-
ide Pellets
3
C1430 Test Method for Determination of Uranium, Oxygen to Ura-
nium, and Oxygen to Metal (O/M) in Sintered Uranium Dioxide
and Gadolinia-Uranium Dioxide Pellets by Atmospheric Equilibra-
tion
4
Spectrochemical Determination of Trace Impurity Elements
3
C1517 Test Method for Determination of Metallic Impurities in Ura-
nium Metal or Compounds by DC-Arc Emission Spectroscopy
2
Total Gas by Hot Vacuum Extraction
Ceramographic Determination of Free Gd O and Free UO to Esti- 17 to 24
2 3 2
mate the Homogeneity of (U,Gd)O Pellets
2
Ceramographic Determination of Average Grain Size by Linear Inter- 25 to 32
cept after Chemical Etching
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.
1
These test methods are under the jurisdiction of ASTM C26 on Nuclear Fuel Cycle and are the direct responsibility of C26.05 on Methods of Test.
Current edition approved JulyJan. 1, 2006.2012. Published August 2006.February 2012. Originally approved in 1981. Last previous edition approved in 19992006 as
C968–99.C968 – 06. DOI: 10.1520/C0968-06.10.1520/C0968-12.
2
Discontinued 1999. See C968 – 94.
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 2005. See C968 – 99.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
C968–12
2. Referenced Documents
3
2.1 ASTM Standards:
C922 Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets
C1347 Practice for Preparation and Dissolution of Uranium Materials for Analysis
C1408 Test Method for Carbon (Total) in Uranium Oxide Powders and Pellets By Direct Combustion-Infrared Detection
Method
C1413 Test Method for Isotopic Analysis of Hydrolyzed Uranium Hexafluoride and Uranyl Nitrate Solutions by Thermal
Ionization Mass Spectrometry
C1430 Test Method for Determination of Uranium, Oxygen to Uranium (O/U), and Oxygen to Metal (O/M) in Sintered
Uranium Dioxide and Gadolinia-Uranium Dioxide Pellets by Atmospheric Equilibration
C1456 Test Method for Determination of Uranium or Gadolinium (or both) in Gadolinium Oxide-Uranium Oxide Pellets
...

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Standard Terminology Relating to Nuclear Materials

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...
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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.
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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)
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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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