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Significance and Use
5.1 Plutonium oxide powder is a component of MOX fuel. This test method can be used to determine whether the carbon and sulfur contents of the PuO2 powder meets the requirements of Specifications and or other requirements as defined by agreement between the nuclear and fuel supplier and the customer.
5.2 MOX is used as a nuclear-reactor fuel. To be used as a fuel, MOX materials must meet specifications on the impurity element contents in them. Examples of these requirements are given in Specification .
5.3 This method is suitable for pure plutonium oxide powder.
1.1 This test method is for the determination of the carbon and sulfur contents in plutonium oxide (PuO2) powder. The method utilizes an induction furnace purged with oxygen for combustion of the sample. Carbon dioxide and sulfur dioxide produced by the combustion are swept into absorption cells and quantified by infrared absorption spectrophotometers. This test method is an alternative to the methods for carbon and sulfur given in Test Method .
1.2 Determination of the carbon and sulfur contents in nuclear-grade sintered mixed oxide (MOX) fuel pellets requires the use of larger samples and is addressed in Test Method .
1.3 The values stated in SI units are to be regarded as standard. Units of measurement in parentheses are included for information only.
1.4 This standard may involve hazardous materials, operations, and equipment. 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.
1.5 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.
C697 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Plutonium Dioxide Powders and Pellets
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
C1128 Guide for Preparation of Working Reference Materials for Use in Analysis of Nuclear Fuel Cycle Materials
C1853 Test Method for The Determination of Carbon (Total) Content in Mixed Oxide ((U, Pu)O2) Sintered Pellets by Direct Combustion-Infrared Detection Method
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
|Link to Active (This link will always route to the current Active version of the standard.)|
ASTM C1865-18, Standard Test Method for The Determination of Carbon and Sulfur Content in Plutonium Oxide Powder by the Direct Combustion-Infrared Spectrophotometer, ASTM International, West Conshohocken, PA, 2018, www.astm.orgBack to Top