Translated Standard: Russian
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Significance and Use

Uranium hexafluoride used to produce nuclear-reactor fuel must meet certain criteria for its isotopic composition. This test method may be used to help determine if sample materials meet the criteria described in Specifications C 787 and C 996 .

1. Scope

1.1 This test method covers a quantitative test method applicable to determining the mass percent of uranium isotopes in uranium hexafluoride (UF ₆ ) samples. This method as described is for concentrations of ²³⁵ U between 0.1 and 10 mass %, and ²³⁴ U and ²³⁶ U between 0.0001 and 0.1 mass %.

1.2 This test method is for laboratory analysis by a gas mass spectrometer with a multi-collector.

1.3 This standard complements Test Methods C 761 , the double-standard method for gas mass spectrometers using a single collector, by providing a method for spectrometers using a multi-collector.

1.4 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.

ASTM Standards

C761 Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium Hexafluoride

C787 Specification for Uranium Hexafluoride for Enrichment

C996 Specification for Uranium Hexafluoride Enriched to Less Than 5 % 235U

C1215 Guide for Preparing and Interpreting Precision and Bias Statements in Test Method Standards Used in the Nuclear Industry

Keywords

double-standard; isotopic; mass spectrometer; multi-collector; spectrometer; uranium hexafluoride; Double-standard multi-collector gas mass spectrometer; Isotopic analysis; Mass spectrometry--nuclear materials/applications; Multi-collector gas mass spectrometer; Uranium hexafluoride (UF 6 );

ICS Code

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

DOI: 10.1520/C1429-99R09E01

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ASTM C1429