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Significance and Use
5.1 MOX is used as a nuclear-reactor fuel. This test method is designed to determine whether the hydrogen content of the pellets meet the requirements of fuel specification. Examples of these requirements are given in Specification . Other requirements may apply based on agreements between the supplier and the customer.
5.2 This method is suitable for all sintered MOX pellets containing up to 15 weight % PuO2 when the UO2 and PuO2 meet the requirements of Specifications and . The method uncertainty is related to the concentration of the hydrogen in the sample. At lower concentrations, the relative uncertainty increases. At hydrogen contents close to the typical hydrogen content specification limit (1.3 μg hydrogen/g U + Pu metal); the combined relative uncertainty at the 95 % confidence level (k = 2) is approximately 30 %.
1.1 This 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 for the determination of moisture in nuclear-grade sintered mixed oxide (MOX) fuel pellets. Test Method 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 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 .
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 and health practices and determine the applicability of regulatory limitations prior to use.
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 (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.
C698 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Mixed Oxides ((U, Pu)O2)
C753 Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
C757 Specification for Nuclear-Grade Plutonium Dioxide Powder for Light Water Reactors
C833 Specification for Sintered (Uranium-Plutonium) Dioxide Pellets for Light Water Reactors
C859 Terminology Relating to Nuclear Materials
C1068 Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
UNSPSC Code 15131500(Nuclear fuel)
|Link to Active (This link will always route to the current Active version of the standard.)|
ASTM C1854-17, Standard Test Method for Determination of Hydrogen (total from all sources) in Mixed Oxide ((U, Pu)O