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ASTM C1726/C1726M-10

(Guide)

Standard Guide for Use of Modeling for Passive Gamma Measurements

Standard Guide for Use of Modeling for Passive Gamma Measurements

SIGNIFICANCE AND USE
The following methods assist in demonstrating regulatory compliance in such areas as safeguards (Special Nuclear Material), inventory control, criticality control, decontamination and decommissioning, waste disposal, holdup and shipping.
This guide can apply to the assay of radionuclides in containers, whose gamma-ray absorption properties can be measured or estimated, for which representative certified standards are not available. It can be applied to in situ measurements, measurement stations, or to laboratory measurements.
Some of the modeling techniques described in the guide are suitable for the measurement of fall-out or natural radioactivity homogenously distributed in soil.
Source-based efficiency calibrations for laboratory geometries may suffer from inaccuracies due to gamma rays being detected in true coincidence. Modeling can be an advantage since it is unaffected by true coincidence summing effects.
SCOPE
1.1 This guide addresses the use of models with passive gamma-ray measurement systems. Mathematical models based on physical principles can be used to assist in calibration of gamma-ray measurement systems and in analysis of measurement data. Some nondestructive assay (NDA) measurement programs involve the assay of a wide variety of item geometries and matrix combinations for which the development of physical standards are not practical. In these situations, modeling may provide a cost-effective means of meeting user’s data quality objectives.
1.2 A scientific knowledge of radiation sources and detectors, calibration procedures, geometry and error analysis is needed for users of this standard. This guide assumes that the user has, at a minimum, a basic understanding of these principles and good NDA practices (see Guide C1592), as defined for an NDA professional in Guide C1490. The user of this standard must have at least a basic understanding of the software used for modeling. Instructions or further training on the use of such software is beyond the scope of this standard.
1.3 The focus of this guide is the use of response models for high-purity germanium (HPGe) detector systems for the passive gamma-ray assay of items. Many of the models described in this guide may also be applied to the use of detectors with different resolutions, such as sodium iodide or lanthanum halide. In such cases, an NDA professional should determine the applicability of sections of this guide to the specific application.
1.4 Techniques discussed in this guide are applicable to modeling a variety of radioactive material including contaminated fields, walls, containers and process equipment.
1.5 This guide does not purport to discuss modeling for “infinite plane” in situ measurements. This discussion is best covered in ANSI N42.28.
1.6 This guide does not purport to address the physical concerns of how to make or set up equipment for in situ measurements but only how to select the model for which the in situ measurement data is analyzed.
1.7 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.
1.8 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.

General Information

Status
Historical
Publication Date
28-Feb-2010
ICS
17.240 - Radiation measurements
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.10 - Non Destructive Assay
Current Stage
Ref Project

Relations

Replaced By
ASTM C1726/C1726M-10(2018) - Standard Guide for Use of Modeling for Passive Gamma Measurements
Effective Date
01-Apr-2018

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ASTM C1726/C1726M-10 - Standard Guide for Use of Modeling for Passive Gamma MeasurementsASTM C1726/C1726M-10 - Standard Guide for Use of Modeling for Passive Gamma Measurements
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ASTM C1726/C1726M-10 - Standard Guide for Use of Modeling for Passive Gamma Measurements
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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: C1726/C1726M − 10
Standard Guide for
1
Use of Modeling for Passive Gamma Measurements
This standard is issued under the fixed designation C1726/C1726M; 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 measurements but only how to select the model for which the
in situ measurement data is analyzed.
1.1 This guide addresses the use of models with passive
gamma-ray measurement systems. Mathematical models based 1.7 The values stated in either SI units or inch-pound units
on physical principles can be used to assist in calibration of are to be regarded separately as standard. The values stated in
gamma-ray measurement systems and in analysis of measure- each system may not be exact equivalents; therefore, each
ment data. Some nondestructive assay (NDA) measurement system shall be used independently of the other. Combining
programs involve the assay of a wide variety of item geom- values from the two systems may result in non-conformance
etries and matrix combinations for which the development of with the standard.
physical standards are not practical. In these situations, mod-
1.8 The values stated in inch-pound units are to be regarded
eling may provide a cost-effective means of meeting user’s
as standard. The values given in parentheses are mathematical
data quality objectives.
conversions to SI units that are provided for information only
1.2 A scientific knowledge of radiation sources and and are not considered standard.
detectors, calibration procedures, geometry and error analysis
2. Referenced Documents
isneededforusersofthisstandard.Thisguideassumesthatthe
2
user has, at a minimum, a basic understanding of these 2.1 ASTM Standards:
principles and good NDA practices (see Guide C1592), as
C1490 GuidefortheSelection,TrainingandQualificationof
defined for an NDA professional in Guide C1490. The user of Nondestructive Assay (NDA) Personnel
this standard must have at least a basic understanding of the
C1592 Guide for Nondestructive Assay Measurements
software used for modeling. Instructions or further training on C1673 Terminology of C26.10 Nondestructive Assay Meth-
the use of such software is beyond the scope of this standard.
ods
3
2.2 Other Standard:
1.3 The focus of this guide is the use of response models for
ANSI N42.28 Performance Standard for the Calibration of
high-purity germanium (HPGe) detector systems for the pas-
Germanium Detectors for In Situ Gamma-Ray Measure-
sive gamma-ray assay of items. Many of the models described
ments
in this guide may also be applied to the use of detectors with
different resolutions, such as sodium iodide or lanthanum
3. Terminology
halide. In such cases, an NDA professional should determine
3.1 See Terminology C1673.
the applicability of sections of this guide to the specific
application.
4. Summary of Guide
1.4 Techniques discussed in this guide are applicable to
4.1 Passive gamma-ray measurements are applied in con-
modeling a variety of radioactive material including contami-
junction with modeling to nondestructively quantify radioac-
nated fields, walls, containers and process equipment.
tivity.
1.5 This guide does not purport to discuss modeling for
4.1.1 Modeling may be used to (1) design and plan the
“infinite plane” in situ measurements. This discussion is best
measurements, (2) establish instrument calibration, (3) inter-
covered in ANSI N42.28.
pret the data acquired, (4) quantify contributions to the
measurementuncertainty, (5)simulatespectra,and (6)evaluate
1.6 This guide does not purport to address the physical
the effectiveness of shielding.
concerns of how to make or set up equipment for in situ
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
1
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Fuel Cycle and is the direct responsibility of Subcommittee C26.10 on Non Standards volume information, refer to the standard’s Document Summary page on
Destructive Assay. the ASTM website.
3
Current edition approved March 1, 2010. Published April 2010. DOI: 10.1520/ Available from American National Standards Institute (ANSI), 25 W. 43rd St.,
C1726_C1726M-10. 4th Floor, New York, NY 10036, http://www.ansi.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1726/C1726M − 10
4.1.2 Various models commonly use analytical, numerical 6.1.3 Matrix identification,
integration and radiation transp
...

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5.1 The TGS provides a nondestructive means of mapping the attenuation characteristics and the distribution of the radionuclide content of items on a voxel by voxel basis. Typically in a TGS analysis a vertical layer (or segment) of an item will be divided into a number of voxels. By comparison, a segmented gamma scanner (SGS) can determine matrix attenuation and radionuclide concentrations only on a segment by segment basis.  
5.2 It has been successfully used to quantify  238Pu, 239Pu, and 235U. SNM loadings from 0.5 g to 200 g of 239Pu (5, 6), from 1 g to 25 g of 235U (7), and from 0.1 to 1 g of 238Pu have been successfully measured. The TGS technique has also been applied to assaying radioactive waste generated by nuclear power plants (NPP). Radioactive waste from NPP is dominated by activation products (for example, 54Mn, 58Co, 60Co,  110mAg) and fission products (for example, 137Cs,  134Cs). The radionuclide activities measured in NPP waste is in the range from 3.7E+04 Bq to 1.0E+07 Bq. Some results of TGS application to non-SNM radionuclides can be found in the literature  (8).  
5.3 The TGS technique is well suited for assaying items that have heterogeneous matrices and that contain a non-uniform radionuclide distribution.  
5.4 Since the analysis results are obtained on a voxel by voxel basis, the TGS technique can in many situations yield more accurate results when compared to other gamma ray techniques such as SGS.  
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SIGNIFICANCE AND USE
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Standard Practices for the Measurement of Radioactivity

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General Information  
6 – 11  
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12 – 22  
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1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.5 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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