ASTM C1457-18
(Test Method)Standard Test Method for Determination of Total Hydrogen Content of Uranium Oxide Powders and Pellets by Carrier Gas Extraction
Standard Test Method for Determination of Total Hydrogen Content of Uranium Oxide Powders and Pellets by Carrier Gas Extraction
SIGNIFICANCE AND USE
5.1 Uranium dioxide is used as a nuclear-reactor fuel. Gadolinium oxide is used as an additive to uranium dioxide. In order to be suitable for this purpose, these materials must meet certain criteria for impurity content. This test method is designed to determine whether the hydrogen content meets Specifications C753, C776, C888, and C922.
SCOPE
1.1 This test method applies to the determination of hydrogen in nuclear-grade uranium oxide powders and pellets to determine compliance with specifications. Gadolinium oxide (Gd2O3) and gadolinium oxide-uranium oxide powders and pellets may also be analyzed using this test method.
1.2 This standard describes a procedure for measuring the total hydrogen content of uranium oxides. The total hydrogen content results from absorbed water, water of crystallization, hydro-carbides and other hydrogenated compounds which may exist as fuel's impurities.
1.3 This test method covers the determination of 0.05 to 200 μg of residual hydrogen.
1.4 This test method describes an electrode furnace carrier gas combustion system equipped with a thermal conductivity detector.
1.5 The preferred system of units is micrograms hydrogen per gram of sample (μg/g sample) or micrograms hydrogen per gram of uranium (μg/g U).
1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.7 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 9.
1.8 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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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: C1457 − 18
Standard Test Method for
Determination of Total Hydrogen Content of Uranium Oxide
1
Powders and Pellets by Carrier Gas Extraction
This standard is issued under the fixed designation C1457; 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. Referenced Documents
2
1.1 This test method applies to the determination of hydro- 2.1 ASTM Standards:
gen in nuclear-grade uranium oxide powders and pellets to C753 Specification for Nuclear-Grade, Sinterable Uranium
determine compliance with specifications. Gadolinium oxide Dioxide Powder
(Gd O ) and gadolinium oxide-uranium oxide powders and C776 Specification for Sintered Uranium Dioxide Pellets for
2 3
pellets may also be analyzed using this test method. Light Water Reactors
C859 Terminology Relating to Nuclear Materials
1.2 This standard describes a procedure for measuring the
C888 Specification for Nuclear-Grade Gadolinium Oxide
total hydrogen content of uranium oxides. The total hydrogen
(Gd O ) Powder
2 3
content results from absorbed water, water of crystallization,
C922 Specification for Sintered Gadolinium Oxide-Uranium
hydro-carbides and other hydrogenated compounds which may
Dioxide Pellets
exist as fuel’s impurities.
1.3 Thistestmethodcoversthedeterminationof0.05to200
3. Terminology
µg of residual hydrogen.
3.1 Definitions:
1.4 This test method describes an electrode furnace carrier
3.1.1 For definitions of terms relating to the nuclear fuel
gas combustion system equipped with a thermal conductivity cycle, refer to Terminology C859.
detector.
4. Summary of Test Method
1.5 The preferred system of units is micrograms hydrogen
4.1 The total hydrogen content is determined using a hy-
per gram of sample (µg/g sample) or micrograms hydrogen per
drogen analyzer. The hydrogen analyzer is based on the carrier
gram of uranium (µg/g U).
gas method using argon or nitrogen as carrier gas. The actual
1.6 The values stated in SI units are to be regarded as
configuration of the system may vary with vendor and model.
standard. No other units of measurement are included in this
4.2 Thesamplestobeanalyzedaredroppedintoapreheated
standard.
graphite crucible, and then, heated up to a temperature of more
1.7 This standard does not purport to address all of the
than 1700°C in a graphite crucible. At that temperature
safety concerns, if any, associated with its use. It is the
hydrogen, oxygen, nitrogen, and carbon monoxide (oxygen is
responsibility of the user of this standard to establish appro-
converted to CO when it reacts with the crucible) are released.
priate safety, health, and environmental practices and deter-
The release gas is purified in the carrier gas stream by
mine the applicability of regulatory limitations prior to use.
oxidation and absorption columns. The hydrogen is separated
For specific hazard statements, see Section 9.
by chromatographic means and analyzed in a thermal conduc-
1.8 This international standard was developed in accor-
tivity detector.
dance with internationally recognized principles on standard-
ization established in the Decision on Principles for the
5. Significance and Use
Development of International Standards, Guides and Recom-
5.1 Uranium dioxide is used as a nuclear-reactor fuel.
mendations issued by the World Trade Organization Technical
Gadolinium oxide is used as an additive to uranium dioxide. In
Barriers to Trade (TBT) Committee.
order to be suitable for this purpose, these materials must meet
certain criteria for impurity content. This test method is
1
This test method is under the jurisdiction ofASTM Committee C26 on Nuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.05 on Methods of
2
Test. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved Feb. 1, 2018. Published February 2018. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
ε1
approved in 2000. Last previous edition approved in 2010 as C1457 – 00 (2010) . Standards volume information, refer to the standard’s Document Summary page on
DOI: 10.1520/C1457-18. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C1457 − 18
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designed to determine whether the hydrogen content meets where such specifications are available. Other grades may be
Specifications C7
...
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: C1457 − 00 (Reapproved 2010) C1457 − 18
Standard Test Method for
Determination of Total Hydrogen Content of Uranium Oxide
1
Powders and Pellets by Carrier Gas Extraction
This standard is issued under the fixed designation C1457; 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—Editorial corrections were made throughout in June 2010.
1. Scope
1.1 This test method applies to the determination of hydrogen in nuclear-grade uranium oxide powders and pellets to determine
compliance with specifications. Gadolinium oxide (Gd O ) and gadolinium oxide-uranium oxide powders and pellets may also be
2 3
analyzed using this test method.
1.2 This standard describes a procedure for measuring the total hydrogen content of uranium oxides. The total hydrogen content
results from absorbed water, water of crystallization, hydro-carbides and other hydrogenated compounds which may exist as fuel’s
impurities.
1.3 This test method covers the determination of 0.05 to 200 μg of residual hydrogen.
1.4 This test method describes an electrode furnace carrier gas combustion system equipped with a thermal conductivity
detector.
1.5 The preferred system of units is micrograms hydrogen per gram of sample (μg/g sample) or micrograms hydrogen per gram
of uranium (μg/g U).
1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.7 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 hazard statements, see Section 9.
1.8 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:
C753 Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
C776 Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors
C859 Terminology Relating to Nuclear Materials
C888 Specification for Nuclear-Grade Gadolinium Oxide (Gd O ) Powder
2 3
C922 Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets
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 total hydrogen content is determined using a hydrogen analyzer. The hydrogen analyzer is based on the carrier gas
method using argon or nitrogen as carrier gas. The actual configuration of the system may vary with vendor and model.
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, 2010Feb. 1, 2018. Published June 2010February 2018. Originally approved in 2000. Last previous edition approved in 20052010 as
ε1
C1457 – 00 (2005).(2010) . DOI: 10.1520/C1457-00R10E01.10.1520/C1457-18.
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 ----------------------
C1457 − 18
4.2 The samples to be analyzed are dropped into a preheated graphite crucible, and then, heated up to a temperature of more
than 1700°C in a graphite crucible. At that temperature hydrogen, oxygen, nitrogen, and carbon monoxide (oxygen is converted
to CO when it reacts with the crucible) are released. The release gas is purified in the carrier gas stream by oxidation and absorption
columns. The hydrogen is separated by chromatographic means and analyzed in a thermal conductivity detector.
5. Significance and Use
5.1 Uranium dioxide is used as a nuclear-reactor fuel. Gadolinium oxide is used as an
...
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