ASTM C1133-96 - 1.1.1996
 
1. Scope

1.1 This test method covers the nondestructive assay of gamma-ray emitting special nuclear materials (SNMs) in low-density scrap or waste, packaged in cylindrical containers (with measured transmission values greater than 1%). High resolution gamma-ray spectroscopy is used to detect and measure the nuclides of interest and to measure and correct for average gamma-ray attenuation in discrete vertical segments of the container. Corrections are also made for counting losses occasioned by signal processing characteristics (1-3).

1.2 Two conditions must be met to optimize assay results as follows:

1.2.1 The particles containing the nuclides of interest must be small to minimize self absorption of emitted gamma radiation.

1.2.2 The mixture of material within a package segment must be reasonably uniform in order to apply an attenuation correction factor, computed from a single measurement of item transmission through the segment.

1.3 The assay technique may be applicable to loadings of from one to several hundred grams of nuclide with more restricted ranges to be applicable, depending on specific packaging and counting equipment considerations. Measured transmission values must be greater than 1% to permit valid attenuation corrections.

1.4 The values stated in SI units are to be regarded as the 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. Specific precautionary statements are given in Section 9.

 
2. Referenced Documents

C1030-26

Standard Test Method for Determination of Plutonium Isotopic Composition by Gamma-Ray Spectrometry

C1128-23

Standard Guide for Preparation of Working Reference Materials for Use in Analysis of Nuclear Fuel Cycle Materials

C1156-26

Standard Guide for Establishing Calibration for a Measurement Method Used to Analyze Nuclear Fuel Cycle Materials

Regulatory Guide 5.53,

Rev. 1, Qualification, Calibration, and Error Estimation Methods for Nondestructive Assay

C1210-21

Standard Guide for Establishing a Measurement System Quality Control Program for Analytical Chemistry Laboratories Within Nuclear Industry

C1458-24

Standard Test Method for Nondestructive Assay of Plutonium, Tritium and 241Am by Calorimetric Assay

E181-23

Standard Guide for Detector Calibration and Analysis of Radionuclides in Radiation Metrology for Reactor Dosimetry

ANSI N42.14

Calibration and Use of Germanium Spectrometers for the Measurement of Gamma-Ray Emission Rates of Radionuclides

C982-03

Standard Guide for Selecting Components for Energy-Dispersive X-Ray Fluorescence (XRF) Systems (Withdrawn 2008)

C1207-10(2018)

Standard Test Method for Nondestructive Assay of Plutonium in Scrap and Waste by Passive Neutron Coincidence Counting