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Significance and Use
This test method is applicable to uranium metal, uranium oxides and compounds soluble in nitric or sulfuric acid, and uranium solutions which can be converted to uranium oxide (U3O8) in a muffle furnace. It may be used to determine the impurities in uranium compounds as listed in Specifications C 753
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 and/or converted to an oxide in a muffle furnace (see Practice C 1347
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 and health practices and determine the applicability of regulatory limitations prior to use.
2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.
C753 Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
C761 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium Hexafluoride
C776 Specification for Sintered Uranium Dioxide Pellets
C788 Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals
C859 Terminology Relating to Nuclear Materials
C967 Specification for Uranium Ore Concentrate
C1347 Practice for Preparation and Dissolution of Uranium Materials for Analysis
E130 Practice for Designation of Shapes and Sizes of Graphite Electrodes
E135 Terminology Relating to Analytical Chemistry for Metals, Ores, and Related Materials
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
UNSPSC Code 15131500(Nuclear fuel)