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ASTM C1428-18

(Test Method)

Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Single–Standard Gas Source Multiple Collector Mass Spectrometer Method

Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Single–Standard Gas Source Multiple Collector Mass Spectrometer Method

SIGNIFICANCE AND USE
5.1 Uranium hexafluoride is a basic material used to produce nuclear reactor fuel. To be suitable for this purpose, the material must meet criteria for isotopic composition. This test method is designed to determine whether the material meets the requirements described in Specifications C787 and C996.
SCOPE
1.1 This test method is applicable to the isotopic analysis of uranium hexafluoride (UF6) with  235U concentrations less than or equal to 5 % and 234U,  236U concentrations of 0.0002 to 0.1 %.  
1.2 This test method may be applicable to the analysis of the entire range of 235U isotopic compositions providing that adequate Certified Reference Materials (CRMs or traceable standards) are available.  
1.3 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.  
1.4 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

General Information

Status
Historical
Publication Date
31-Oct-2018
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

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ASTM C1428-18 - Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Single–Standard Gas Source Multiple Collector Mass Spectrometer MethodASTM C1428-18 - Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Single–Standard Gas Source Multiple Collector Mass Spectrometer Method
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REDLINE ASTM C1428-18 - Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Single–Standard Gas Source Multiple Collector Mass Spectrometer MethodREDLINE ASTM C1428-18 - Standard Test Method for Isotopic Analysis of Uranium Hexafluoride by Single–Standard Gas Source Multiple Collector Mass Spectrometer Method
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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: C1428 − 18
Standard Test Method for
Isotopic Analysis of Uranium Hexafluoride by
Single–Standard Gas Source Multiple Collector Mass
1
Spectrometer Method
This standard is issued under the fixed designation C1428; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope 2.2 Other Document:
USEC-651 Uranium Hexafluoride: A Manual of Good
1.1 This test method is applicable to the isotopic analysis of
3
Handling Practices
235
uranium hexafluoride (UF ) with U concentrations less than
6
234 236
or equal to 5 % and U, U concentrations of 0.0002 to
3. Terminology
0.1 %.
3.1 For definitions of terms relating to the nuclear fuel
cycle, refer to Terminology C859.
1.2 This test method may be applicable to the analysis of the
235
entire range of U isotopic compositions providing that
4. Summary of Test Method
adequate Certified Reference Materials (CRMs or traceable
standards) are available.
4.1 The unknown sample and a CRM or traceable standard
whose isotopic composition is close to that of the sample are
1.3 This standard does not purport to address all of the
234
introduced in sequence into the mass spectrometer, and U,
safety concerns, if any, associated with its use. It is the
235 236 238
U, U, and U ions are focused through corresponding
responsibility of the user of this standard to establish appro-
collector slits to the four separate collectors. Measurements are
priate safety, health, and environmental practices and deter-
234 235 236
made that are proportional to the ratios of U, U, or U
mine the applicability of regulatory limitations prior to use. 238
to U. With the known composition of the CRM or traceable
1.4 This international standard was developed in accor-
standard, these ratios of molar ratios permit calculation of the
234 235 236
dance with internationally recognized principles on standard-
U, U, and U contents. Memory corrections are ap-
ization established in the Decision on Principles for the
plied based on the periodic measurement of two CRMs or
Development of International Standards, Guides and Recom-
traceable standards.
mendations issued by the World Trade Organization Technical
5. Significance and Use
Barriers to Trade (TBT) Committee.
5.1 Uranium hexafluoride is a basic material used to pro-
2. Referenced Documents
duce nuclear reactor fuel. To be suitable for this purpose, the
2 material must meet criteria for isotopic composition. This test
2.1 ASTM Standards:
method is designed to determine whether the material meets
C787 Specification for Uranium Hexafluoride for Enrich-
the requirements described in Specifications C787 and C996.
ment
C859 Terminology Relating to Nuclear Materials
6. Apparatus
C996 Specification for Uranium Hexafluoride Enriched to
6.1 A gas source multiple collector mass spectrometer with
235
Less Than 5 % U
the following attributes:
6.1.1 The resolving power of the mass spectrometer is not
less than 500. The resolving power (R) is calculated from the
1
235 + 238 +
This test method is under the jurisdiction of ASTM Committee C26 on Nuclear
registered mass spectrum of both the UF and UF
5 5
Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of
isotopes as follows:
Test.
Current edition approved Nov. 1, 2018. Published December 2018. Originally
a·M
R 5 (1)
approved in 1999. Last previous edition approved in 2011 as C1428 – 11. DOI:
b·ΔM
10.1520/C1428-18.
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 Available from United States Enrichment Corporation, 6903 Rockledge Drive,
the ASTM website. Bethesda, MD 20817.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1428 − 18
SH X X SL
where: 0.0002 to 0.01 C /C #4,C /C #4; in concen-
234~236! 234~236! 234~236! 234~236!
235 + 238 + SH X X SL
tration range 0.01 to 0.1 C /C #3,C /C #3.
a = distance between centers of the UF and UF
234~236! 234~236! 234~236! 234~236!
5 5
peaks,
238 +
b = peak width of the UF isotope (10 % valley),
9. Procedure
5
238 +
M = 333 − mass(u) UF , and
5 A typical sequence for the analytical determination is X, S,
235 +
ΔM = 3 = 333 − 330, 330 − mass(u) UF .
5
X, S, where X and S mean the introduction of the sample
and the CRM or traceable standard, respectively. Each intro-
6.1.2 The abundance sensitivity of the mass spectrometer is
−5
specified as l
...

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: C1428 − 11 C1428 − 18
Standard Test Method for
Isotopic Analysis of Uranium Hexafluoride by
Single–Standard Gas Source Multiple Collector Mass
1
Spectrometer Method
This standard is issued under the fixed designation C1428; 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
235
1.1 This test method is applicable to the isotopic analysis of uranium hexafluoride (UF ) with U concentrations less than or
6
234 236
equal to 5 % and U, U concentrations of 0.0002 to 0.1 %.
235
1.2 This test method may be applicable to the analysis of the entire range of U isotopic compositions providing that adequate
Certified Reference Materials (CRMs or traceable standards) are available.
1.3 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 safety, health, and environmental practices and determine the
applicability of regulatory limitations prior to use.
1.4 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.
2. Referenced Documents
2
2.1 ASTM Standards:
C787 Specification for Uranium Hexafluoride for Enrichment
C859 Terminology Relating to Nuclear Materials
235
C996 Specification for Uranium Hexafluoride Enriched to Less Than 5 % U
2.2 Other Document:
3
USEC-651 Uranium Hexafluoride: A Manual of Good Handling Practices
3. Terminology
3.1 For definitions of terms relating to the nuclear fuel cycle, refer to Terminology C859.
4. Summary of Test Method
4.1 The unknown sample and a CRM or traceable standard whose isotopic composition is close to that of the sample are
234 235 236 238
introduced in sequence into the mass spectrometer, and U, U, U, and U ions are focused through corresponding
234 235 236
collector slits to the four separate collectors. Measurements are made that are proportional to the ratios of U, U, or U
238 234
to U. With the known composition of the CRM or traceable standard, these ratios of molar ratios permit calculation of the U,
235 236
U, and U contents. Memory corrections are applied based on the periodic measurement of two CRMs or traceable standards.
5. Significance and Use
5.1 Uranium hexafluoride is a basic material used to produce nuclear reactor fuel. To be suitable for this purpose, the material
must meet criteria for isotopic composition. This test method is designed to determine whether the material meets the requirements
described in Specifications C787 and C996.
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 March 1, 2011Nov. 1, 2018. Published April 2011December 2018. Originally approved in 1999. Last previous edition approved in 20052011
as C1428–99(2005).C1428 – 11. DOI: 10.1520/C1428-11.10.1520/C1428-18.
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
Available from United States Enrichment Corporation, 6903 Rockledge Drive, Bethesda, MD 20817.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1428 − 18
6. Apparatus
6.1 A gas source multiple collector mass spectrometer with the following attributes:
6.1.1 The resolving power of the mass spectrometer is not less than 500. The resolving power (R) is calculated from the
235 + 238 +
registered mass spectrum of both the UF and UF isotopes as follows:
5 5
a·M
R 5 (1)
b·ΔM
wherewhere:
235 + 238 +
a = distance between centers of the UF and UF peaks,
5 5
238 +
b = peak width of the UF isotope (10 % valley),
5
238 +
M = 333 − mass(u) UF , and
5
235 +
ΔM = 3 = 333 − 330, 330 − mass(u) UF .
5
−5 238 +
6.1.2 The abundance sensitivity of the mass spectrometer is specified as less than 1×10 as contribu
...

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Standard Test Method for Quantitative Determination of 241Am in Plutonium by Gamma-Ray Spectrometry

SIGNIFICANCE AND USE
5.1 This test method allows the determination of 241Am in a plutonium solution without separation of the americium from the plutonium. It is generally applicable to any solution containing 241Am.  
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ASTM C1168-23(Practice)
Standard Practice for Preparation and Dissolution of Plutonium Materials for Analysis

SIGNIFICANCE AND USE
5.1 Plutonium and uranium mixtures are used as nuclear reactor fuels. For use as a nuclear reactor fuel, the material must meet certain criteria for combined uranium and plutonium content, effective fissile content, and impurity content as described in Specifications C757 and C833. After dissolution using one of the procedures described in this practice, the material is assayed for plutonium and uranium to determine if the content is correct as specified by the purchaser.  
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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 C1108-23(Test Method)
Standard Test Method for Plutonium by Controlled-Potential Coulometry

SIGNIFICANCE AND USE
5.1 Factors governing selection of a method for the determination of plutonium include available quantity of sample, sample purity, desired level of reliability, and equipment.  
5.1.1 This test method determines 5 mg to 20 mg of plutonium with prior dissolution using Practice C1168.  
5.1.2 This test method calculates plutonium mass fraction in solutions and solids using an electrical calibration based upon Ohm’s Law and the Faraday Constant.  
5.1.3 Chemical standards are used for quality control. When prior chemical separation of plutonium is necessary to remove interferences, the quality control standards should be included with each chemical separation batch (9).  
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.
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1.1 This test method describes the determination of dissolved plutonium from unirradiated nuclear-grade (that is, high-purity) materials by controlled-potential coulometry. Controlled-potential coulometry may be performed in a choice of supporting electrolytes, such as 0.9 mol/L (0.9 M) HNO3, 1 mol/L (1 M) HClO4, 1 mol/L (1 M) HCl, 5 mol/L (5 M) HCl, and 0.5 mol/L (0.5 M) H2SO4. Limitations on the use of selected supporting electrolytes are discussed in Section 6. Optimum quantities of plutonium for this procedure are 5 mg to 20 mg.  
1.2 Plutonium-bearing materials are radioactive and toxic. Adequate laboratory facilities, such as gloved boxes, fume hoods, controlled ventilation, etc., along with safe techniques must be used in handling specimens containing these materials.  
1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are 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.  
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 C1204-14(2023)(Test Method)
Standard Test Method for Uranium in Presence of Plutonium by Iron(II) Reduction in Phosphoric Acid Followed by Chromium(VI) Titration

SIGNIFICANCE AND USE
4.1 Factors governing selection of a method for the determination of uranium include available quantity of sample, sample purity, desired level of reliability, and equipment availability.  
4.2 This test method is suitable for samples between 20 mg to 300 mg of uranium, is applicable to fast breeder reactor (FBR)-mixed oxides having a uranium to plutonium ratio of 2.5 and greater, is tolerant towards most metallic impurity elements usually specified for FBR-mixed oxide fuel, and uses no special equipment.  
4.3 The ruggedness of the titration method has been studied for both the volumetric (6) and the weight (7) titration of uranium with dichromate.
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1.1 This test method covers unirradiated uranium-plutonium mixed oxide having a uranium to plutonium ratio of 2.5 and greater. The presence of larger amounts of plutonium (Pu) that give lower uranium to plutonium ratios may give low analysis results for uranium (U) (1)2, if the amount of plutonium together with the uranium is sufficient to slow the reduction step and prevent complete reduction of the uranium in the allotted time. Use of this test method for lower uranium to plutonium ratios may be possible, especially when 20 mg to 50 mg quantities of uranium are being titrated rather than the 100 mg to 300 mg in the study cited in Ref (1). Confirmation of that information should be obtained before this test method is used for ratios of uranium to plutonium less than 2.5.  
1.2 The amount of uranium determined in the data presented in Section 12 was 20 mg to 50 mg. However, this test method, as stated, contains iron in excess of that needed to reduce the combined quantities of uranium and plutonium in a solution containing 300 mg of uranium with uranium to plutonium ratios greater than or equal to 2.5. Solutions containing up to 300 mg uranium with uranium to plutonium ratios greater than or equal to 2.5 have been analyzed (1) using the reagent volumes and conditions as described in Section 10.  
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. For specific hazard statements, see Section 8.  
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 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.
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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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