ASTM C1133-03
(Test Method)Standard Test Method for Nondestructive Assay of Special Nuclear Material in Low Density Scrap and Waste by Segmented Passive Gamma-Ray Scanning
Standard Test Method for Nondestructive Assay of Special Nuclear Material in Low Density Scrap and Waste by Segmented Passive Gamma-Ray Scanning
SIGNIFICANCE AND USE
Segmented gamma-ray scanning provides a nondestructive means of measuring the nuclide content of scrap and waste where the specific nature of the matrix and the chemical form and relationship between the nuclide and matrix may be unknown.
The procedure can serve as a diagnostic tool that provides a vertical profile of transmission and nuclide concentration within the item.
Sample preparation is generally limited to good waste/scrap segregation practices that produce relatively homogeneous items that are required for any successful waste/inventory management and assay scheme, regardless of the measurement method used. Also, process knowledge should be used, when available, as part of a waste management program to complement information on sample parameters, container properties, and the appropriateness of calibration factors.
SCOPE
1.1 This test method covers the transmission-corrected nondestructive assay (NDA) of gamma-ray emitting special nuclear materials (SNMs), most commonly 235U, 239Pu, and 241Am, in low-density scrap or waste, packaged in cylindrical containers. The method can also be applied to NDA of other gamma-emitting nuclides including fission products. High-resolution gamma-ray spectroscopy is used to detect and measure the nuclides of interest and to measure and correct for gamma-ray attenuation in a series of horizontal segments (collimated gamma detector views) of the container. Corrections are also made for counting losses occasioned by signal processing limitations (1-3).
1.2 There are currently several systems in use or under development for determining the attenuation corrections for NDA of radioisotopic materials (4-8). A related technique, tomographic gamma-ray scanning (TGS), is not included in this test method (9,10).
1.2.1 This test method will cover two implementations of the Segmented Gamma Scanning (SGS) procedure: (1) Isotope Specific (Mass) Calibration, the original SGS procedure, uses standards of known radionuclide masses to determine detector response in a mass versus corrected count rate calibration that applies only to those specific radionuclides for which it is calibrated, and (2) Efficiency Curve Calibration, an alternative method, typically uses non-SNM radionuclide sources to determine system detection efficiency vs. gamma energy and thereby calibrate for all gamma-emitting radionuclides of interest (11). These two methods will be covered in detail in the remainder of the main body of this test method and Annex A1.
1.2.1.1 Efficiency Curve Calibration, over the energy range for which the efficiency is defined, has the advantage of providing calibration for many gamma-emitting nuclide for which half-life and gamma emission intensity data are available.
1.3 The assay technique may be applicable to loadings up to several hundred grams of nuclide in a 208-L (55-gal) drum, with more restricted ranges to be applicable depending on specific packaging and counting equipment considerations.
1.4 Measured transmission values must be available for use in calculation of segment-specific attenuation corrections at the energies of analysis.
1.5 A related method, SGS with calculated correction factors based on sample content and density, is not included in this standard.
1.6 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
1.7 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 8.
General Information
Relations
Standards Content (Sample)
NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information.
Designation:C1133–03
Standard Test Method for
Nondestructive Assay of Special Nuclear Material in Low-
Density Scrap and Waste by Segmented Passive Gamma-
1
Ray Scanning
This standard is issued under the fixed designation C1133; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope providing calibration for many gamma-emitting nuclide for
which half-life and gamma emission intensity data are avail-
1.1 This test method covers the transmission-corrected non-
able.
destructive assay (NDA) of gamma-ray emitting special
235 239
1.3 The assay technique may be applicable to loadings up to
nuclear materials (SNMs), most commonly U, Pu,
241
several hundred grams of nuclide in a 208-L (55-gal) drum,
and Am, in low-density scrap or waste, packaged in cylin-
with more restricted ranges to be applicable depending on
drical containers. The method can also be applied to NDA of
specific packaging and counting equipment considerations.
other gamma-emitting nuclides including fission products.
1.4 Measured transmission values must be available for use
High-resolution gamma-ray spectroscopy is used to detect and
incalculationofsegment-specificattenuationcorrectionsatthe
measure the nuclides of interest and to measure and correct for
energies of analysis.
gamma-ray attenuation in a series of horizontal segments
1.5 A related method, SGS with calculated correction fac-
(collimated gamma detector views) of the container. Correc-
torsbasedonsamplecontentanddensity,isnotincludedinthis
tions are also made for counting losses occasioned by signal
2
standard.
processing limitations (1-3).
1.6 The values stated in SI units are to be regarded as the
1.2 There are currently several systems in use or under
standard. The values given in parentheses are for information
development for determining the attenuation corrections for
only.
NDA of radioisotopic materials (4-8). A related technique,
1.7 This standard does not purport to address all of the
tomographic gamma-ray scanning (TGS), is not included in
safety concerns, if any, associated with its use. It is the
this test method (9,10).
responsibility of the user of this standard to establish appro-
1.2.1 This test method will cover two implementations of
priate safety and health practices and determine the applica-
the Segmented Gamma Scanning (SGS) procedure: (1) Isotope
bility of regulatory limitations prior to use. Specific precau-
Specific (Mass) Calibration, the original SGS procedure, uses
tionary statements are given in Section 8.
standards of known radionuclide masses to determine detector
response in a mass versus corrected count rate calibration that
2. Referenced Documents
applies only to those specific radionuclides for which it is
3
2.1 ASTM Standards:
calibrated, and (2) Efficiency Curve Calibration, an alternative
C982 Guide for Selecting Components for Energy-
method, typically uses non-SNM radionuclide sources to
4
Dispersive X-Ray Fluorescence (XRF) Systems
determine system detection efficiency vs. gamma energy and
C1030 Test Method for Determination of Plutonium Isoto-
thereby calibrate for all gamma-emitting radionuclides of
pic Composition by Gamma-Ray Spectrometry
interest(11).Thesetwomethodswillbecoveredindetailinthe
C1128 Guide for Preparation of Working Reference Mate-
remainder of the main body of this test method andAnnexA1.
rials for Use in Analysis of Nuclear Fuel Cycle Materials
1.2.1.1 Efficiency Curve Calibration, over the energy range
C1156 Guide for Establishing Calibration for a Measure-
for which the efficiency is defined, has the advantage of
ment Method Used to Analyze Nuclear Fuel Cycle Mate-
rials
1
This test method is under the jurisdiction ofASTM Committee C26 on Nuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.10 on Nondestruc-
3
tive Assay. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved July 10, 2003. Published September 2003. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 1996. Last previous edition approved in 1996 as C1133 – 96. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/C1133-03. the ASTM website.
2 4
The boldface numbers in parentheses refer to the list of references at the end of Withdrawn. The last approved version of this historical standard is referenced
this test method. on www.astm.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
1
---------------------- Page: 1 ---------------------
...
Questions, Comments and Discussion
Ask us and Technical Secretary will try to provide an answer. You can facilitate discussion about the standard in here.