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ASTM C1295-14

(Test Method)

Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution

Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution

SIGNIFICANCE AND USE
4.1 Specific gamma-ray emitting radionuclides in UF6 are identified and quantified using a high-resolution gamma-ray energy analysis system, which includes a high-resolution germanium detector. This test method shall be used to meet the health and safety specifications of C787, C788, and C996 regarding applicable fission products in reprocessed uranium solutions. This test method may also be used to provide information to parties such as conversion facilities on the level of uranium decay products in such materials. Pa-231 is a specific uranium decay product that may be present in uranium ore concentrate and is amenable to analysis by gamma spectrometry.
SCOPE
1.1 This test method covers the measurement of gamma energy emitted from fission and decay products in uranium hexafluoride (UF6) and uranyl nitrate solution. It is intended to provide a method for demonstrating compliance with UF6 specifications C787 and C996, uranyl nitrate specification C788, and uranium ore concentrate specification C967.  
1.2 The lower limit of detection is 5000 MeV Bq/kg (MeV/kg per second) of uranium and is the square root of the sum of the squares of the individual reporting limits of the nuclides to be measured. The limit of detection was determined on a pure, aged natural uranium (ANU) solution. The value is dependent upon detector efficiency and background.  
1.3 The fission product nuclides to be measured are 106Ru/ 106Rh, 103Ru, 137Cs,  144Ce,  144Pr,  141Ce,  95Zr,  95Nb, and  125Sb. Among the uranium decay product nuclides that may be measured is 231Pa. Other gamma energy-emitting fission and uranium decay nuclides present in the spectrum at detectable levels should be identified and quantified as required by the data quality objectives.  
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
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 and health practices and determine the applicability of regulatory limitations prior to use.

General Information

Status
Historical
Publication Date
14-Jun-2014
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 C1295-13 - Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution
Effective Date
15-Jun-2014
Replaced By
ASTM C1295-15 - Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution
Effective Date
01-Jun-2015
Referred By
ASTM C799-19 - Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Nuclear-Grade Uranyl Nitrate Solutions
Effective Date
15-Jun-2014
Referred By
ASTM C787-20 - Standard Specification for Uranium Hexafluoride for Enrichment
Effective Date
15-Jun-2014
Referred By
ASTM C1462-21 - Standard Specification for Uranium Metal Enriched to Less Than 20 % <sup> 235</sup >U
Effective Date
15-Jun-2014
Referred By
ASTM C788-03(2021) - Standard Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals
Effective Date
15-Jun-2014
Referred By
ASTM C757-16(2021) - Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors
Effective Date
15-Jun-2014
Referred By
ASTM C761-18 - Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium Hexafluoride
Effective Date
15-Jun-2014

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ASTM C1295-14 - Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate SolutionASTM C1295-14 - Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution
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REDLINE ASTM C1295-14 - Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate SolutionREDLINE ASTM C1295-14 - Standard Test Method for Gamma Energy Emission from Fission and Decay Products in Uranium Hexafluoride and Uranyl Nitrate Solution
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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:C1295 −14
StandardTest Method for
Gamma Energy Emission from Fission and Decay Products
1
in Uranium Hexafluoride and Uranyl Nitrate Solution
This standard is issued under the fixed designation C1295; 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 C761Test Methods for Chemical, Mass Spectrometric,
Spectrochemical, Nuclear, and RadiochemicalAnalysis of
1.1 This test method covers the measurement of gamma
Uranium Hexafluoride
energy emitted from fission and decay products in uranium
C787Specification for Uranium Hexafluoride for Enrich-
hexafluoride (UF ) and uranyl nitrate solution. It is intended to
6
ment
provide a method for demonstrating compliance with UF
6
C788Specification for Nuclear-Grade Uranyl Nitrate Solu-
specifications C787 and C996, uranyl nitrate specification
tion or Crystals
C788, and uranium ore concentrate specification C967.
C967Specification for Uranium Ore Concentrate
1.2 The lower limit of detection is 5000 MeV Bq/kg
C996Specification for Uranium Hexafluoride Enriched to
235
(MeV/kg per second) of uranium and is the square root of the
Less Than 5 % U
sum of the squares of the individual reporting limits of the
C1022Test Methods for Chemical and Atomic Absorption
nuclidestobemeasured.Thelimitofdetectionwasdetermined
Analysis of Uranium-Ore Concentrate
on a pure, aged natural uranium (ANU) solution. The value is
D3649PracticeforHigh-ResolutionGamma-RaySpectrom-
dependent upon detector efficiency and background.
etry of Water
106
1.3 The fission product nuclides to be measured are Ru/
106 103 137 144 144 141 95 95 125 3. Summary of Test Method
Rh, Ru, Cs, Ce, Pr, Ce, Zr, Nb, and Sb.
3.1 A solution of the uranium sample is counted on a
Among the uranium decay product nuclides that may be
231
high-resolutiongamma-rayspectrometrysystem.Theresulting
measured is Pa. Other gamma energy-emitting fission and
spectrum is analyzed to determine the identity and activity of
uranium decay nuclides present in the spectrum at detectable
the gamma-ray-emitting radioactive fission and decay prod-
levels should be identified and quantified as required by the
ucts. The number of counts recorded from one or more of the
data quality objectives.
peaks identified with each fission nuclide is converted to
1.4 The values stated in SI units are to be regarded as
disintegrationsofthatnuclidepersecond(Bq).Thegamma-ray
standard. No other units of measurement are included in this
energy for a fission nuclide is calculated by multiplying the
standard.
number of disintegrations per second of the nuclide by the
1.5 This standard does not purport to address all of the
mean gamma-ray energy emission rate of the nuclide. The
safety concerns, if any, associated with its use. It is the
calculated gamma-ray energy emission rates for all observed
responsibility of the user of this standard to establish appro-
fission nuclides are summed, then divided by the mass of the
priate safety and health practices and determine the applica-
uranium in the sample to calculate the overall rate of gamma
bility of regulatory limitations prior to use.
energy production in units of million electron volts per second
231
perkilogramofuranium.Decayproductnuclidessuchas Pa
2. Referenced Documents
will be separately quantified and reported based on specific
2
2.1 ASTM Standards:
needs.
4. Significance and Use
1
ThistestmethodisunderthejurisdictionofASTMCommitteeC26onNuclear
4.1 Specific gamma-ray emitting radionuclides in UF are
6
Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of
identified and quantified using a high-resolution gamma-ray
Test.
energy analysis system, which includes a high-resolution
Current edition approved June 15, 2014. Published July 2014. Originally
germaniumdetector.Thistestmethodshallbeusedtomeetthe
approved in 1995. Last previous edition approved in 2013 as C1295–13. DOI:
10.1520/C1295-14.
health and safety specifications of C787, C788, and C996
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
regarding applicable fission products in reprocessed uranium
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
solutions. This test method may also be used to provide
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. information to parties such as conversion facilities on the level
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1295−14
of uranium decay products in such materials. Pa-
...

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: C1295 − 13 C1295 − 14
Standard Test Method for
Gamma Energy Emission from Fission and Decay Products
1
in Uranium Hexafluoride and Uranyl Nitrate Solution
This standard is issued under the fixed designation C1295; 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 This test method covers the measurement of gamma energy emitted from fission and decay products in uranium hexafluoride
(UF ) and uranyl nitrate solution. It is intended to provide a method for demonstrating compliance with UF specifications C787
6 6
and C996 and , uranyl nitrate specification C788, and uranium ore concentrate specification C967.
1.2 The lower limit of detection is 5000 MeV Bq/kg (MeV/kg per second) of uranium and is the square root of the sum of the
squares of the individual reporting limits of the nuclides to be measured. The limit of detection was determined on a pure, aged
natural uranium (ANU) solution. The value is dependent upon detector efficiency and background.
106 106 103
1.3 The fission product nuclides to be measured are are Ru/ Rh, Ru,
137 144 144 141 95 95 125 231
Cs, Ce, Pr, Ce, Zr, Nb, and Sb. Among the uranium decay product nuclides that may be measured is Pa. Other
gamma energy-emitting fission and uranium decay nuclides present in the spectrum at detectable levels should be identified and
quantified as required by the data quality objectives.
1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
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 and health practices and determine the applicability of regulatory
limitations prior to use.
2. Referenced Documents
2
2.1 ASTM Standards:
C761 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium
Hexafluoride
C787 Specification for Uranium Hexafluoride for Enrichment
C788 Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals
C967 Specification for Uranium Ore Concentrate
235
C996 Specification for Uranium Hexafluoride Enriched to Less Than 5 % U
C1022 Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore Concentrate
D3649 Practice for High-Resolution Gamma-Ray Spectrometry of Water
3. Summary of Test Method
3.1 A solution of the uranium sample is counted on a high-resolution gamma-ray spectrometry system. The resulting spectrum
is analyzed to determine the identity and activity of the gamma-ray-emitting radioactive fission and decay products. The number
of counts recorded from one or more of the peaks identified with each fission nuclide is converted to disintegrations of that nuclide
per second (Bq). The gamma-ray energy for a fission nuclide is calculated by multiplying the number of disintegrations per second
of the nuclide by the mean gamma-ray energy emission rate of the nuclide. The calculated gamma-ray energy emission rates for
all observed fission nuclides are summed, then divided by the mass of the uranium in the sample to calculate the overall rate of
gamma energy production in units of million electron volts per second per kilogram of uranium. Decay product nuclides such as
231
Pa will be separately quantified and reported based on specific needs.
1
This test method is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of Test.
Current edition approved Feb. 15, 2013June 15, 2014. Published March 2013July 2014. Originally approved in 1995. Last previous edition approved in 20052013 as
C1295 – 05.C1295 – 13. DOI: 10.1520/C1295-13.10.1520/C1295-14.
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.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1295 − 14
4. Significance and Use
4.1 Specific gamma-ray emitting radionuclides in UF are identified and quantified using a high-resolution ga
...

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SIGNIFICANCE AND USE
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Section  
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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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