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ASTM C1430-07

(Test Method)

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

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

SIGNIFICANCE AND USE
Uranium dioxide is used as a nuclear-reactor fuel. This test method is designed to determine whether the percent uranium and O/U or O/M content meet Specifications C 776 and C 922.
SCOPE
1.1 This test method applies to the determination of uranium, the oxygen to uranium (O/U) ratio in sintered uranium dioxide pellets, and the oxygen to metal (O/M) ratio in sintered gadolinium oxide-uranium dioxide pellets with a Gd2O3  concentration of up to 12 weight %. The O/M calculations assume that the gadolinium and uranium oxides are present in a metal dioxide solid solution.
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 hazards statements, see Section 8.

General Information

Status
Historical
Publication Date
31-Jan-2007
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 C1430-00 - 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-Feb-2007
Replaced By
ASTM C1430-07(2011)e1 - 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-Jun-2011
Referred By
ASTM C968-19 - Standard Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets
Effective Date
01-Feb-2007

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ASTM C1430-07 - 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 EquilibrationASTM C1430-07 - 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
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ASTM C1430-07 - 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
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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:C1430–07
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
1
Equilibration
This standard is issued under the fixed designation C1430; 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 3. Summary of Test Method
1.1 This test method applies to the determination of ura- 3.1 The uranium, and either O/U or O/M, are determined by
nium, the oxygen to uranium (O/U) ratio in sintered uranium measuring the weight change of a sintered pellet after it has
dioxidepellets,andtheoxygentometal(O/M)ratioinsintered been exposed to an equilibrating atmosphere to bring it to the
gadolinium oxide-uranium dioxide pellets with a Gd O con- stoichiometric condition. Sintered pellets are weighed and
2 3
centration of up to 12 weight %. The O/M calculations assume loaded into a sample boat. The boat is placed in a tube furnace
that the gadolinium and uranium oxides are present in a metal capable of holding a temperature of 800 6 10°C. The furnace
dioxide solid solution. is purged with a moist gas flow of 4 % hydrogen and 96 %
1.2 This standard does not purport to address all of the argon or nitrogen to remove all air. The temperature of the
safety concerns, if any, associated with its use. It is the furnace is raised to 800°C and held at this temperature with
responsibility of the user of this standard to establish appro- constant gas flow for 4 h. The furnace then is turned off and
priate safety and health practices and determine the applica- allowed to cool, with gas purge on, to room temperature. The
bilityofregulatorylimitationspriortouse.Forspecifichazards samples are removed from the furnace and reweighed.
statements, see Section 8. 3.2 The weight change, gadolinia content, and chemical
impurity content are used to calculate % uranium and the O/U
2. Referenced Documents
or O/M.
2
2.1 ASTM Standards:
4. Significance and Use
C696 Test Methods for Chemical, Mass Spectrometric, and
Spectrochemical Analysis of Nuclear-Grade Uranium Di- 4.1 Uranium dioxide is used as a nuclear-reactor fuel. This
oxide Powders and Pellets test method is designed to determine whether the percent
C776 Specification for Sintered Uranium Dioxide Pellets uranium and O/U or O/M content meet Specifications C776
C922 Specification for Sintered Gadolinium Oxide- and C922.
Uranium Dioxide Pellets
5. Interferences
C968 Test Methods for Analysis of Sintered Gadolinium
5.1 Parameters for temperature, gas composition, gas flow,
Oxide-Uranium Dioxide Pellets
C1287 Test Method for Determination of Impurities in and moist air purge must be monitored and maintained care-
fully within the limits set in the procedure.
Nuclear Grade Uranium Compounds by Inductively
Coupled Plasma Mass Spectrometry 5.2 This test method assumes that chemical impurities meet
Specifications C776 and C922 limits. Potential method inter-
ferences from higher impurity concentrations will require
1
This test method is under the jurisdiction ofASTM Committee C26 on Nuclear evaluation.
Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of
5.3 Furnace tubes or boats made from metals that oxidize
Test.
under the test conditions may prevent proper equilibration by
Current edition approved Feb. 1, 2007. Published March 2007. Originally
consuming available oxygen.
approved in 2000. Last previous edition approved in 2000 as C1430–00. DOI:
10.1520/C1430-07.
5.4 Preciseweighingofsamplesiscriticaltotheaccuracyof
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
this test method.
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
5.5 Loss of weight due to pellet chipping would invalidate
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. the analysis. Handle pellets with care.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1

---------------------- Page: 1 ----------------------
C1430–07
5.6 This test method assumes that pellets are sintered. It 8. Hazards and Precautions
does not correct for moisture or volatile additives.
8.1 Take proper safety precautions for handling uranium.
5.7 This test method assumes that UO -Gd O pellets have
2 2 3 8.2 Thefurnace,sampletubeandsampleboatsareheatedto
formed a solid solution; however, the error from incomplete
800°C. Care must be taken to avoid burns.
dissolution of Gd O would be very small (see the calculation
2 3
8.3 Exercise a
...

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18  
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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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    6 pages
    English language
    sale 15% off