ASTM C1295-98
Historical Standard: ASTM C1295-98 Standard Test Method for Gamma Energy Emission from Fission Products in Uranium Hexafluoride
SUPERSEDED (see Active link, below)
ASTM C1295
1. Scope
1.1 This test method covers the measurement of gamma energy emitted from fission products in uranium hexafluoride (UF ). It is intended to provide a method for demonstrating compliance with UF Specifications C787 and C996 and replace the ion chamber measurement technique.
1.2 The lower limit of detection is 5000 MeV Bq/kg (MeV/kg per second) of uranium and is the square root of the sum of the squares of the individual reporting limits of the nuclides to be measured. The limit of detection was determined on a pure, aged natural uranium (ANU) solution. The value is dependent upon detector efficiency and background.
1.3 The nuclides to be measured are 106 Ru/ 106 Rh, 103 Ru, 144 Ce, 144 Pr, 141 Ce, 95 Zr, 95 Nb, 125 Sb. Other gamma energy-emitting fission nuclides that are identified should be measured and reported.
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
C788 Specification for Nuclear-Grade Uranyl Nitrate Solution or Crystals
C996 Specification for Uranium Hexafluoride Enriched to Less Than 5 % 235U
D3649 Practice for High-Resolution Gamma-Ray Spectrometry of Water
Keywords
fission products; high purity germanium detector; gamma energy; gamma-ray spectrometry; uranium hexafluoride; uranium nitrate;
ICS Code
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
DOI: 10.1520/C1295-98
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