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
5.1 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 C776 and C922.
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.  
1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
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. For specific hazards statements, see Section 9.  
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.

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Publication Date
31-Jan-2018
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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
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REDLINE 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
English language
7 pages
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Standards Content (Sample)

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.
Designation: 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
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.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope C776SpecificationforSinteredUraniumDioxidePelletsfor
Light Water Reactors
1.1 This test method applies to the determination of
C859Terminology Relating to Nuclear Materials
uranium, the oxygen to uranium (O/U) ratio in sintered
C922SpecificationforSinteredGadoliniumOxide-Uranium
uraniumdioxidepellets,andtheoxygentometal(O/M)ratioin
Dioxide Pellets
sintered gadolinium oxide-uranium dioxide pellets with a
C968Test Methods for Analysis of Sintered Gadolinium
Gd O concentration of up to 12 weight %. The O/M calcula-
2 3
Oxide-Uranium Dioxide Pellets
tions assume that the gadolinium and uranium oxides are
C1287Test Method for Determination of Impurities in
present in a metal dioxide solid solution.
Nuclear Grade Uranium Compounds by Inductively
1.2 The values stated in SI units are to be regarded as
Coupled Plasma Mass Spectrometry
standard. No other units of measurement are included in this
standard.
3. Terminology
1.3 This standard does not purport to address all of the
3.1 Definitions:
safety concerns, if any, associated with its use. It is the
3.1.1 For definitions of terms relating to the nuclear fuel
responsibility of the user of this standard to establish appro-
cycle, refer to Terminology C859.
priate safety, health, and environmental practices and deter-
mine the applicability of regulatory limitations prior to use.
4. Summary of Test Method
For specific hazards statements, see Section 9.
1.4 This international standard was developed in accor-
4.1 Theuranium,andeitherO/UorO/M,aredeterminedby
dance with internationally recognized principles on standard-
measuring the weight change of a sintered pellet after it has
ization established in the Decision on Principles for the
been exposed to an equilibrating atmosphere to bring it to the
Development of International Standards, Guides and Recom-
stoichiometric condition. Sintered pellets are weighed and
mendations issued by the World Trade Organization Technical
loaded into a sample boat.The boat is placed in a tube furnace
Barriers to Trade (TBT) Committee.
capable of holding a temperature of 800 6 10°C. The furnace
is purged with a moist gas flow of 4% hydrogen and 96%
2. Referenced Documents
argon or nitrogen to remove all air. The temperature of the
2
2.1 ASTM Standards: furnace is raised to 800°C and held at this temperature with
constant gas flow for 4 h. The furnace then is turned off and
C696Test Methods for Chemical, Mass Spectrometric, and
SpectrochemicalAnalysis of Nuclear-Grade Uranium Di- allowed to cool, with gas purge on, to room temperature. The
samples are removed from the furnace and reweighed.
oxide Powders and Pellets
4.2 The weight change, gadolinia content, and chemical
impurity content are used to calculate % uranium and the O/U
1
ThistestmethodisunderthejurisdictionofASTMCommitteeC26onNuclear
or O/M.
Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of
Test.
Current edition approved Feb. 1, 2018. Published February 2018. Originally
5. Significance and Use
ε1
approved in 2000. Last previous edition approved in 2011 as C1430–07 (2011) .
DOI: 10.1520/C1430-18.
5.1 Uranium dioxide is used as a nuclear-reactor fuel. This
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
test method is designed to determine whether the percent
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
uranium and O/U or O/M content meet Specifications C776
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. and C922.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1430 − 18
6. Interferences 7.4 Assorted Connectors, Tubing, Flasks, Stoppers, and
Delivery Tubes—The purge gas is passed through a humidifier,
6.1 Parameters for temperature, gas composition, gas flow,
intothetubefurnace.Abubblerflaskisattachedtothefurnace
and moist air purge must be monitored and maintained care-
outlet to monitor gas flow (see Fig. 1).
fully within the limits set
...

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.
´1
Designation: C1430 − 07 (Reapproved 2011) 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
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
ε NOTE—A units statement was added editorially in June 2011.
1. 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 Gd O concentration of
2 3
up to 12 weight %. The O/M calculations assume that the gadolinium and uranium oxides are present in a metal dioxide solid
solution.
1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
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 safety, health, and healthenvironmental practices and determine the
applicability of regulatory limitations prior to use. For specific hazards statements, see Section 89.
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:
C696 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide
Powders and Pellets
C776 Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors
C859 Terminology Relating to Nuclear Materials
C922 Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets
C968 Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets
C1287 Test Method for Determination of Impurities in Nuclear Grade Uranium Compounds by Inductively Coupled Plasma
Mass Spectrometry
3. Terminology
3.1 Definitions:
3.1.1 For definitions of terms relating to the nuclear fuel cycle, refer to Terminology C859.
4. Summary of Test Method
4.1 The uranium, and either O/U or O/M, are determined by measuring the weight change of a sintered pellet after it has been
exposed to an equilibrating atmosphere to bring it to the stoichiometric condition. Sintered pellets are weighed and loaded into a
sample boat. The boat is placed in a tube furnace capable of holding a temperature of 800 6 10°C. The furnace is purged with
a moist gas flow of 4 % hydrogen and 96 % argon or nitrogen to remove all air. The temperature of the furnace is raised to 800°C
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 June 1, 2011Feb. 1, 2018. Published June 2011February 2018. Originally approved in 2000. Last previous edition approved in 20072011 as
ε1
C1430C1430 – 07 (2011) –07. DOI: 10.1520/C1430-07R11E01.10.1520/C1430-18.
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.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1430 − 18
and held at this temperature with constant gas flow for 4 h. The furnace then is turned off and allowed to cool, with gas purge on,
to room temperature. The samples are removed from the furnace and reweighed.
4.2 The weight change, gadolinia content, and chemical impurity content are used to calculate % uranium and the O/U or O/M.
5. Significance and Use
5.1 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 C776 and C922.
6. Interferences
6.1 Parameters for tempe
...

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