Significance and Use
The test method is capable of measuring uranium isotopic abundances of 234U, 235U, 236U and 238U as required by Specifications C 787 and C 996.
1. Scope
1.1 This test method covers the isotopic abundance analysis of 234U, 235U, 236U and 238U in samples of hydrolysed uranium hexafluoride (UF6) by inductively coupled plasma source, multicollector, mass spectrometry (ICP-MC-MS). The method applies to material with 235U abundance in the range of 0.2 to 6 % mass. This test method is also described in ASTM STP 1344.
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.
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
D1193 Specification for Reagent Water
Other Document
STP1344 Applications of Inductively Coupled Plasma-Mass Spectrometry (ICP-MS) to Radionuclide Determinations
Keywords
ICP-MC-MS; ICP-MS; inductively coupled plasma mass spectrometer; internal reference; isotope ratio; isotopic abundance; mass bias; mass bias factor; mass bias parameter; memory; multi-collector; thorium; uranium; Hydrolysed uranium hexafluoride (UF6); ICP-MS (inductively-coupled plasma-mass spectrometry); Isotopic analysis; Mass spectrometry--nuclear materials/applications; Multi-collector inductively-coupled mass spectrometry; Uranium hexafluoride (UF6);
ICS Code
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
DOI: 10.1520/C1477-08
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Citing ASTM Standards
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