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ASTM C 1457 : 2018

Current

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

Available format(s)

Hardcopy , PDF

Language(s)

English

Published date

01-02-2018

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.

Committee
C 26
DocumentType
Test Method
Pages
4
PublisherName
American Society for Testing and Materials
Status
Current
Supersedes

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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