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  • ASTM
    C1517-24 Standard Test Method for Determination of Metallic Impurities in Uranium Metal or Compounds by DC-Arc Emission Spectroscopy
    Edition: 2024
    $86.11
    Unlimited Users per year

Description of ASTM-C1517 2024

ASTM C1517-24

Active Standard: Standard Test Method for Determination of Metallic Impurities in Uranium Metal or Compounds by DC-Arc Emission Spectroscopy




ASTM C1517

Scope

1.1 This test method describes the steps necessary for the preparation and determination of impurity metals in uranium metal and uranium compounds by DC arc emission spectroscopy.

1.2 The method is valid for those materials that can be dissolved in acid or converted to an oxide in a muffle furnace, or both (see Practice C1347).

1.3 This method uses the carrier distillation technique to selectively carry the impurities into the arc, leaving the uranium oxide in the electrode. If it is necessary to determine the carrier metal (usually a silver or strontium, or gallium compound) as an impurity, another technique must be chosen for that element.

1.4 Units—The values stated in SI units are to be regarded as standard. The values given in parentheses are for information only.

1.5 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.

1.6 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.


Keywords

carrier distillation; dc-arc; emission spectroscopy; impurities in uranium;


ICS Code

ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)


DOI: 10.1520/C1517-24

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