ASTM C 1457 : 2018
Current
The latest, up-to-date edition.
Standard Test Method for Determination of Total Hydrogen Content of Uranium Oxide Powders and Pellets by Carrier Gas Extraction
Hardcopy , PDF
English
01-02-2018
Committee |
C 26
|
DocumentType |
Test Method
|
Pages |
4
|
PublisherName |
American Society for Testing and Materials
|
Status |
Current
|
Supersedes |
1.1This 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.
1.2This 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.
1.3This test method covers the determination of 0.05 to 200 μg of residual hydrogen.
1.4This test method describes an electrode furnace carrier gas combustion system equipped with a thermal conductivity detector.
1.5The preferred system of units is micrograms hydrogen per gram of sample (μg/g sample) or micrograms hydrogen per gram of uranium (μg/g U).
1.6The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.7This 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.
1.8This 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.
ASTM C 696 : 2011 | Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Uranium Dioxide Powders and Pellets |
ASTM C 968 : 2012 | Standard Test Methods for Analysis of Sintered Gadolinium Oxide-Uranium Dioxide Pellets |
ASTM C 859 : 2023 | Standard Terminology Relating to Nuclear Materials |
ASTM C 922 : 2021 | Standard Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets for Light Water Reactors |
ASTM C 859 : 2014 : REV B | Standard Terminology Relating to Nuclear Materials |
ASTM C 776 : 2017 : R2022 | Standard Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors |
ASTM C 859 : 2024 | Standard Terminology Relating to Nuclear Materials |
ASTM C 922 : 2014 | Standard Specification for Sintered Gadolinium Oxide-Uranium Dioxide Pellets |
ASTM C 859 : 2022 | Standard Terminology Relating to Nuclear Materials |
ASTM C 859 : 2022 : REV A | Standard Terminology Relating to Nuclear Materials |
ASTM C 753 : 2016 : REV A | Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder |
ASTM C 776 : 2017 | Standard Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors |
ASTM C 753 : 2016 : REV A : R2021 | Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder |
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