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ASTM C 1854 : 2017

Current

Current

The latest, up-to-date edition.

Standard Test Method for Determination of Hydrogen (total from all sources) in Mixed Oxide ((U, Pu)O2) Sintered Pellets by the Inert Gas Fusion Technique Followed by Thermal Conductivity Measurement

Available format(s)

Hardcopy , PDF

Language(s)

English

Published date

01-06-2017

£48.38
Excluding VAT

CONTAINED IN VOL. 12.01, 2017 Defines the determination of hydrogen in nuclear-grade mixed oxides of uranium and plutonium ((U, Pu)O[2]) sintered fuel pellets.

Committee
C 26
DocumentType
Test Method
Pages
6
PublisherName
American Society for Testing and Materials
Status
Current

1.1This test method covers the determination of hydrogen in nuclear-grade mixed oxides of uranium and plutonium ((U, Pu)O2) sintered fuel pellets. This test method is an alternative to Test Method C698 for the determination of moisture in nuclear-grade sintered mixed oxide (MOX) fuel pellets. Test Method C698 describes the detection of moisture in mixed oxides using a coulometric, electrolytic moisture analyzer. Although the main source of H2 in the fuel pellets is moisture, there could be other sources. The MOX pellet Specification C833 specifies a limit for hydrogen from all sources, not only moisture. The inert gas fusion followed by thermal conductivity detector specified in this test method allows for detection of hydrogen from all sources. Therefore, this test method can be used to determine the limit specified in C833.

1.2The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.

1.3This 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.

1.4This 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 833 : 2017 Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors
ASTM C 859 : 2023 Standard Terminology Relating to Nuclear Materials
ASTM C 859 : 2014 : REV B Standard Terminology Relating to Nuclear Materials
ASTM C 757 : 1990 : R1996 : EDT 1 Standard Specification for Nuclear-Grade Plutonium Dioxide Powder, Sinterable
ASTM C 859 : 2024 Standard Terminology Relating to Nuclear Materials
ASTM C 833 : 2023 Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors
ASTM C 757 : 2016 : EDT 1 Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors
ASTM C 1068 : 1996 : EDT 1 Standard Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry
ASTM C 1068 : 2003 : R2011 Standard Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry
ASTM C 1068 : 2015 Standard Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry
ASTM C 698 : 2016 : REDLINE Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O<inf>2</inf>)
ASTM C 757 : 2016 : R2021 Standard Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors
ASTM C 1068 : 2021 Standard Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry
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 1068 : 2003 Standard Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry
ASTM C 833 : 2017 : REDLINE Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors
ASTM C 1068 : 2015 : REDLINE Standard Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry
ASTM C 753 : 2016 : REV A : R2021 Standard Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder

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