ASTM C1133/C1133M-10
(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.
Item 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 item parameters, container properties, and the appropriateness of calibration factors.
To obtain the lowest detection levels, a two-pass assay should be used. The two-pass assay also reduces problems related to potential interferences between transmission peaks and assay peaks. For items with higher activities, a single-pass assay may be used to increase throughput.
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, 11).
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 (12).
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 nuclides 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 item content and density, is not included in this standard.
1.6 The values stated in either SI units or inch-pound units are to be regarded separately as standard. The values stated in each system may not be exact equivalents; therefore, each system shall be used independently of the other. Combining values from the two systems may result in non-conformance with the standard.
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...
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Designation: C1133/C1133M − 10
Standard Test Method for
Nondestructive Assay of Special Nuclear Material in Low-
Density Scrap and Waste by Segmented Passive Gamma-
1
Ray Scanning
ThisstandardisissuedunderthefixeddesignationC1133/C1133M;thenumberimmediatelyfollowingthedesignationindicatestheyear
of original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.
A superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope 1.2.1.1 Efficiency Curve Calibration, over the energy range
for which the efficiency is defined, has the advantage of
1.1 This test method covers the transmission-corrected non-
providing calibration for many gamma-emitting nuclides for
destructive assay (NDA) of gamma-ray emitting special
235 239 which half-life and gamma emission intensity data are avail-
nuclear materials (SNMs), most commonly U, Pu,
241 able.
and Am, in low-density scrap or waste, packaged in cylin-
drical containers. The method can also be applied to NDA of 1.3 Theassaytechniquemaybeapplicabletoloadingsupto
other gamma-emitting nuclides including fission products. several hundred grams of nuclide in a 208-L [55-gal] drum,
High-resolution gamma-ray spectroscopy is used to detect and with more restricted ranges to be applicable depending on
measure the nuclides of interest and to measure and correct for specific packaging and counting equipment considerations.
gamma-ray attenuation in a series of horizontal segments
1.4 Measured transmission values must be available for use
(collimated gamma detector views) of the container. Correc-
incalculationofsegment-specificattenuationcorrectionsatthe
tions are also made for counting losses occasioned by signal
energies of analysis.
2
processing limitations (1-3).
1.5 A related method, SGS with calculated correction fac-
1.2 There are currently several systems in use or under
tors based on item content and density, is not included in this
development for determining the attenuation corrections for
standard.
NDA of radioisotopic materials (4-8). A related technique,
1.6 The values stated in either SI units or inch-pound units
tomographic gamma-ray scanning (TGS), is not included in
are to be regarded separately as standard. The values stated in
this test method (9, 10, 11).
each system may not be exact equivalents; therefore, each
1.2.1 This test method will cover two implementations of
system shall be used independently of the other. Combining
theSegmentedGammaScanning(SGS)procedure:(1)Isotope
values from the two systems may result in non-conformance
Specific (Mass) Calibration, the original SGS procedure, uses
with the standard.
standards of known radionuclide masses to determine detector
response in a mass versus corrected count rate calibration that 1.7 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the
applies only to those specific radionuclides for which it is
calibrated, and (2) Efficiency Curve Calibration, an alternative responsibility of the user of this standard to establish appro-
priate safety and health practices and determine the applica-
method, typically uses non-SNM radionuclide sources to
determine system detection efficiency vs. gamma energy and bility of regulatory limitations prior to use. Specific precau-
tionary statements are given in Section 10.
thereby calibrate for all gamma-emitting radionuclides of
interest (12).
2. Referenced Documents
3
2.1 ASTM Standards:
1
ThistestmethodisunderthejurisdictionofASTMCommitteeC26onNuclear
C1030TestMethodforDeterminationofPlutoniumIsotopic
Fuel Cycle and is the direct responsibility of Subcommittee C26.10 on Non
Composition by Gamma-Ray Spectrometry
Destructive Assay.
Current edition approved Jan. 1, 2010. Published February 2010. Originally
3
approved in 1996. Last previous edition approved in 2003 as C1133–03. DOI: For referenced ASTM standards, visit the ASTM website, www.astm.org, or
10.1520/C1133_C1133M-10. contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
2
Theboldfacenumbersinparenthesesrefertothelistofreferencesattheendof Standards volume information, refer to the standard’s Document Summary page on
this test method. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C1133/C1133M − 10
C1128Guide for Preparation of Working Reference Materi- emission intensity of the radionuclide, and the corrected count
als for Use in Analysis of Nuclear Fuel Cycle Materials rate and detector efficiency at the peak energy.
C1156Guide for Establishing Calibration for a Measure-
4.3 The assay item is rotated about its vertical axis and
ment
...
This document is not anASTM standard and is intended only to provide the user of anASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation:C1133–03 Designation:C1133/C1133M–10
Standard Test Method for
Nondestructive Assay of Special Nuclear Material in Low-
Density Scrap and Waste by Segmented Passive Gamma-
1
Ray Scanning
ThisstandardisissuedunderthefixeddesignationC1133/C1133M;thenumberimmediatelyfollowingthedesignationindicatestheyear
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
1.1 This test method covers the transmission-corrected nondestructive assay (NDA) of gamma-ray emitting special nuclear
235 239 241
materials (SNMs), most commonly U, Pu, and Am, 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
spectroscopyisusedtodetectandmeasurethenuclidesofinterestandtomeasureandcorrectforgamma-rayattenuationinaseries
of horizontal segments (collimated gamma detector views) of the container. Corrections are also made for counting losses
2
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).Arelated technique, tomographic gamma-ray scanning (TGS), is not included in this test method (9,
10, 11).
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
responseinamassversuscorrectedcountratecalibrationthatappliesonlytothosespecificradionuclidesforwhichitiscalibrated,
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(12). 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 nuclides for which half-life and gamma emission intensity data are available.
1.3 Theassaytechniquemaybeapplicabletoloadingsuptoseveralhundredgramsofnuclideina208-L(55-gal)[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.
1.5A related method, SGS with calculated correction factors based on sample content and density, is not included in this
standard.
1.6The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
1.5 Arelated method, SGS with calculated correction factors based on item content and density, is not included in this standard.
1.6 The values stated in either SI units or inch-pound units are to be regarded separately as standard. The values stated in each
system may not be exact equivalents; therefore, each system shall be used independently of the other. Combining values from the
two systems may result in non-conformance with the standard.
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 810.
1
This test method is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.10 on Nondestructive
Assay.
Current edition approved July 10, 2003. Published September 2003. Originally approved in 1996. Last previous edition approved in 1996 as C1133–96. DOI:
10.1520/C1133-03.on Non Destructive Assay.
Current edition approved Jan. 1, 2010. Published February 2010. Originally approved in 1996. Last previous edition approved in 2003 as C1133 – 03. DOI:
10.1520/C1133_C1133M-10.
2
The boldface numbers in parentheses refer to the list of references at the end of this test method.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West C
...
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