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ASTM C1750-17

(Guide)

Standard Guide for Development, Verification, Validation, and Documentation of Simulated High-Level Tank Waste

Standard Guide for Development, Verification, Validation, and Documentation of Simulated High-Level Tank Waste

SCOPE
1.1 Intent:  
1.1.1 The intent of this guideline is to provide general considerations for the development, verification, validation, and documentation of high-level waste (HLW) tank simulants. Due to the expense and hazards associated with obtaining and working with actual wastes, especially radioactive wastes, simulants are used in a wide variety of applications including process and equipment development and testing, equipment acceptance testing, and plant commissioning. This standard guide facilitates a consistent methodology for development, preparation, verification, validation, and documentation of waste simulants.  
1.2 This guideline provides direction on (1) defining simulant use, (2) defining simulant-design requirements, (3) developing a simulant preparation procedure, (4) verifying and validating that the simulant meets design requirements, and (5) documenting simulant-development activities and simulant preparation procedures.  
1.3 Applicability:  
1.3.1 This guide is intended for persons and organizations tasked with developing HLW simulants to mimic certain characteristics and properties of actual wastes. The process for simulant development, verification, validation, and documentation is shown schematically in Fig. 1. Specific approval requirements for the simulants developed under this guideline are not provided. This topic is left to the performing organization.
FIG. 1 Simulant Development, Verification, Validation, and Documentation Flowsheet  
1.3.2 While this guide is directed at HLW simulants, much of the guidance may also be applicable to other aqueous based solutions and slurries.  
1.3.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.4 User Caveats:  
1.4.1 This guideline is not a substitute for sound chemistry and chemical engineering skills, proven practices and experience. It is not intended to be prescriptive but rather to provide considerations for the development and use of waste simulants.  
1.4.2 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.

General Information

Status
Historical
Publication Date
14-Nov-2017
ICS
13.030.30 - Special wastes
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.13 - Spent Fuel and High Level Waste
Current Stage
Ref Project

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ASTM C1750-17 - Standard Guide for Development, Verification, Validation, and Documentation of Simulated High-Level Tank WasteASTM C1750-17 - Standard Guide for Development, Verification, Validation, and Documentation of Simulated High-Level Tank Waste
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REDLINE ASTM C1750-17 - Standard Guide for Development, Verification, Validation, and Documentation of Simulated High-Level Tank WasteREDLINE ASTM C1750-17 - Standard Guide for Development, Verification, Validation, and Documentation of Simulated High-Level Tank Waste
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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:C1750 −17
Standard Guide for
Development, Verification, Validation, and Documentation of
1
Simulated High-Level Tank Waste
This standard is issued under the fixed designation C1750; 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 1.4.1 This guideline is not a substitute for sound chemistry
and chemical engineering skills, proven practices and experi-
1.1 Intent:
ence. It is not intended to be prescriptive but rather to provide
1.1.1 The intent of this guideline is to provide general
considerationsforthedevelopmentanduseofwastesimulants.
considerations for the development, verification, validation,
1.4.2 This standard does not purport to address all of the
and documentation of high-level waste (HLW) tank simulants.
safety concerns, if any, associated with its use. It is the
Due to the expense and hazards associated with obtaining and
responsibility of the user of this standard to establish appro-
working with actual wastes, especially radioactive wastes,
priate safety, health, and environmental practices and deter-
simulants are used in a wide variety of applications including
mine the applicability of regulatory limitations prior to use.
process and equipment development and testing, equipment
1.5 This international standard was developed in accor-
acceptance testing, and plant commissioning. This standard
dance with internationally recognized principles on standard-
guide facilitates a consistent methodology for development,
ization established in the Decision on Principles for the
preparation, verification, validation, and documentation of
Development of International Standards, Guides and Recom-
waste simulants.
mendations issued by the World Trade Organization Technical
1.2 This guideline provides direction on (1) defining simu-
Barriers to Trade (TBT) Committee.
lant use, (2) defining simulant-design requirements, (3) devel-
oping a simulant preparation procedure, (4) verifying and
2. Referenced Documents
validating that the simulant meets design requirements, and (5)
2
2.1 ASTM Standards:
documenting simulant-development activities and simulant
C859 Terminology Relating to Nuclear Materials
preparation procedures.
C1109 Practice for Analysis of Aqueous Leachates from
1.3 Applicability:
Nuclear Waste Materials Using Inductively Coupled
1.3.1 This guide is intended for persons and organizations
Plasma-Atomic Emission Spectroscopy
tasked with developing HLW simulants to mimic certain
C1111 Test Method for Determining Elements in Waste
characteristics and properties of actual wastes. The process for
StreamsbyInductivelyCoupledPlasma-AtomicEmission
simulant development, verification, validation, and documen-
Spectroscopy
tation is shown schematically in Fig. 1. Specific approval
C1752 Guide for Measuring Physical and Rheological Prop-
requirements for the simulants developed under this guideline
erties of Radioactive Solutions, Slurries, and Sludges
are not provided. This topic is left to the performing organi-
D4129 Test Method for Total and Organic Carbon in Water
zation.
by High Temperature Oxidation and by Coulometric
1.3.2 While this guide is directed at HLW simulants, much
Detection
of the guidance may also be applicable to other aqueous based
2.2 Environmental Protection Agency SW-846 Methods:
solutions and slurries.
Method 3010A Acid digestion of Aqueous Samples and
1.3.3 The values stated in SI units are to be regarded as the
Extracts for total metals for Analysis by FLAA or ICP
standard. The values given in parentheses are for information
Spectroscopy
only.
Method 3050B Acid Digestion of Sediments, Sludges and
1.4 User Caveats:
Soils
Method 3051A Microwave Assisted Acid Digestion of
1
This specification is under the jurisdiction of ASTM Committee C26 on
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.13 on
2
Spent Fuel and High Level Waste. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved Nov. 15, 2017. Published December 2017. Originally contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
approved in 2011. Last previous edition approved in 2011 as C1750 – 11. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/C1750-17. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1750−17
FIG. 1Simulant Development, Verification, Validation, and Documentation Flowsheet
Sediments, Sludges and Soils 3.3.3 GFC—Glas
...

This document is not an ASTM standard and is intended only to provide the user of an ASTM 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: C1750 − 11 C1750 − 17
Standard Guide for
Development, Verification, Validation, and Documentation of
1
Simulated High-Level Tank Waste
This standard is issued under the fixed designation C1750; 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
1.1 Intent:
1.1.1 The intent of this guideline is to provide general considerations for the development, verification, validation, and
documentation of high-level waste (HLW) tank simulants. Due to the expense and hazards associated with obtaining and working
with actual wastes, especially radioactive wastes, simulants are used in a wide variety of applications including process and
equipment development and testing, equipment acceptance testing, and plant commissioning. This standard guide facilitates a
consistent methodology for development, preparation, verification, validation, and documentation of waste simulants.
1.2 This guideline provides direction on (1) defining simulant use, (2) defining simulant-design requirements, (3) developing
a simulant preparation procedure, (4) verifying and validating that the simulant meets design requirements, and (5) documenting
simulant-development activities and simulant preparation procedures.
1.3 Applicability:
1.3.1 This guide is intended for persons and organizations tasked with developing HLW simulants to mimic certain
characteristics and properties of actual wastes. The process for simulant development, verification, validation, and documentation
is shown schematically in Fig. 1. Specific approval requirements for the simulants developed under this guideline are not provided.
This topic is left to the performing organization.
1.3.2 While this guide is directed at HLW simulants, much of the guidance may also be applicable to other aqueous based
solutions and slurries.
1.3.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
1.4 User Caveats:
1.4.1 This guideline is not a substitute for sound chemistry and chemical engineering skills, proven practices and experience.
It is not intended to be prescriptive but rather to provide considerations for the development and use of waste simulants.
1.4.2 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 safety, health, and healthenvironmental 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.
2. Referenced Documents
2
2.1 ASTM Standards:
C859 Terminology Relating to Nuclear Materials
C1109 Practice for Analysis of Aqueous Leachates from Nuclear Waste Materials Using Inductively Coupled Plasma-Atomic
Emission Spectroscopy
C1111 Test Method for Determining Elements in Waste Streams by Inductively Coupled Plasma-Atomic Emission Spectroscopy
C1752 Guide for Measuring Physical and Rheological Properties of Radioactive Solutions, Slurries, and Sludges
D4129 Test Method for Total and Organic Carbon in Water by High Temperature Oxidation and by Coulometric Detection
1
This specification is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.13 on Spent Fuel and
High Level Waste.
Current edition approved June 1, 2011Nov. 15, 2017. Published September 2011December 2017. DOI: 10.1520/Originally approved in 2011. Last previous edition
approved in 2011 as C1750C1750 – 11.-11. DOI: 10.1520/C1750-17.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1750 − 17
FIG. 1 Simulant Development, Verification, Validation, and
...

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ASTM C1682-21(Guide)
Standard Guide for Characterization of Spent Nuclear Fuel in Support of Interim Storage, Transportation and Geologic Repository Disposal

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5.1 In order to demonstrate conformance to regulatory requirements and support the post-closure repository performance assessment information is required about the attributes, characteristics, and behavior of the SNF. These properties of the SNF in turn support the transport, interim storage, and repository pre-closure safety analyses, and repository post-closure performance assessment. In the United States, the interim dry storage of commercial LWR SNF is regulated per the Code of Federal Regulations, Title 10, Part 72, which requires that the cladding must not sustain during the interim storage period any “gross” damage sufficient to release fuel from the cladding into the container environment. In other countries, the appropriate governing body will set regulations regarding interim dry storage of commercial LWR SNF. However, cladding damage insufficient to allow the release of fuel during the interim storage period may still occur in the form of small cracks or pinholes that can develop into much larger defects. These cracks/pinholes could be sufficient to classify the fuel as “failed fuel” or “breached fuel” per the definitions given in Section 3 for repository disposal purposes, because they could allow contact of water vapor or liquid with the spent fuel matrix and thus provide a pathway for radionuclide release from the waste form. Therefore SNF characterization should be adequate to determine the amount of “failed fuel” for either usage as required. This could involve the examination of reactor operating records, ultrasonic testing, sipping, and analysis of the residual water and drying kinetics of the spent fuel assemblies or canisters.  
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SIGNIFICANCE AND USE
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1.3 A list of the elements determined in waste streams and the corresponding lower reporting limit is found in Table 1.  
1.4 This test method has been used successfully for treatment of a large variety of waste solutions and industrial process liquids. The composition of such samples is highly variable, both between waste stream types and within a single waste stream. As a result of this variability, a single acid digestion scheme may not be expected to succeed with all sample matrices. Certain elements may be recovered on a semi-quantitative basis, while most results will be highly quantitative.  
1.5 This test method should be used by analysts experienced in the use of ICP-AES, the interpretation of spectral and non-spectral interferences, and procedures for their correction.  
1.6 No detailed operating instructions are provided because of differences among various makes and models of suitable ICP-AES instruments. Instead, the analyst shall follow the instructions provided by the manufacturer of the particular instrument. This test method does not address comparative accuracy of different devices or the precision between instruments of the same make and model.  
1.7 This test method contains notes that are explanatory and are not part of the mandatory requirements of the method.  
1.8 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.9 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.  
1.10 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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ASTM C1174-20(Guide)
Standard Guide for Evaluation of Long-Term Behavior of Materials Used in Engineered Barrier Systems (EBS) for Geological Disposal of High-Level Radioactive Waste

SIGNIFICANCE AND USE
5.1 This guide supports the development of material behavior models that can be used to estimate performance of the EBS materials during the post-closure period of a high-level nuclear waste repository for times much longer than can be tested directly. This guide is intended for modeling the degradation behaviors of materials proposed for use in an EBS designed to contain radionuclides over tens of thousands of years and more. There is both national and international recognition of the importance of the use and long-term performance of engineered materials in geologic repository design. Use of the models developed following the approaches described in this guide is intended to address established regulations, such as:  
5.1.1 U.S. Public Law 97–425, the Nuclear Waste Policy Act of 1982, provides for the deep geologic disposal of high-level radioactive waste through a system of multiple barriers. These barriers include engineered barriers designed to prevent the migration of radionuclides out of the engineered system, and the geologic host medium that provides an additional transport barrier between the engineered system and biosphere. The regulations of the U.S. Nuclear Regulatory Commission for geologic disposal require a performance confirmation program to provide data through tests and analyses, where practicable, that demonstrate engineered systems and components that are designed or assumed to act as barriers after permanent closure are functioning as intended and anticipated.  
5.1.2 IAEA Safety Requirements specify that engineered barriers shall be designed and the host environment shall be selected to provide containment of the radionuclides associated with the wastes.  
5.1.3 The Swedish Regulatory Authority has provided general advice to the repository developer that the application of best available technique be followed in connection with disposal, which means that the siting, design, construction, and operation of the repository and appurtenant syste...
SCOPE
1.1 This guide addresses how various test methods and data analyses can be used to develop models for the evaluation of the long-term alteration behavior of materials used in an engineered barrier system (EBS) for the disposal of spent nuclear fuel (SNF) and other high-level nuclear waste in a geologic repository. The alteration behavior of waste forms and EBS materials is important because it affects the retention of radionuclides within the disposal system either directly, as in the case of waste forms in which the radionuclides are initially immobilized, or indirectly, as in the case of EBS containment materials that restrict the ingress of groundwater or the egress of radionuclides that are released as the waste forms degrade.  
1.2 The purpose of this guide is to provide a scientifically-based strategy for developing models that can be used to estimate material alteration behavior after a repository is permanently closed (that is, in the post-closure period). Because the timescale involved with geological disposal precludes direct validation of predictions, mechanistic understanding of the processes based on detailed data and models and consideration of the range of uncertainty are recommended.  
1.3 This guide addresses the scientific bases and uncertainties in material behavior models and the impact on the confidence in the EBS design criteria and repository performance assessments using those models. This includes the identification and use of conservative assumptions to address uncertainty in the long-term performance of materials.  
1.3.1 Steps involved in evaluating the performance of waste forms and EBS materials include problem definition, laboratory and field testing, modeling of individual and coupled processes, and model confirmation.  
1.3.2 The estimates of waste form and EBS material performance are based on models derived from theoretical considerations, expert judgments, and interpretations of d...

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ASTM
ASTM C1463-19(Practice)
Standard Practices for Dissolving Glass Containing Radioactive and Mixed Waste for Chemical and Radiochemical Analysis

ABSTRACT
These practices cover three standard technique for dissolving glass samples containing radioactive, nuclear, and mixed wastes. These techniques used together or independently will produce solutions that can be analyzed by inductively coupled plasma atomic emission spectroscopy (ICP-AES), inductively coupled plasma mass spectrometry (ICP-MS), atomic absorption spectrometry (AAS), radiochemical methods and wet chemical techniques for major components, minor components and radionuclides. The practices for dissolving silicate matrix samples each require the sample to be initially dried and ground to a fine powder. The first practice involves the mixing and fusion of the sample with sodium tetraborate (Na2B4O7) and sodium carbonate (Na2CO4) in a muffle for a given amount of time and temperature. The sample is then cooled, dissolved in hydrochloric acid, and diluted to appropriate volume for analyses. The second practice, on the other hand, involves the fusion of the sample with potassium hydroxide (KOH) or sodium peroxide (Na2O2) using an electric bunsen burner, dissolving the fused sample in water and dilute HCl, and making to volume for analyses. Finally, the third practice involves the dissolution of the sample using a microwave oven. The ground sample is digested in a microwave oven using a mixture of hydrofluoric (HF) and nitric (HNO3) acids. Boric acid is added to the resulting solution to complex excess fluoride ions.
SCOPE
1.1 These practices cover techniques suitable for dissolving glass samples that may contain nuclear wastes. These techniques used together or independently will produce solutions that can be analyzed by inductively coupled plasma atomic emission spectroscopy (ICP-AES), inductively coupled plasma mass spectrometry (ICP-MS), atomic absorption spectrometry (AAS), radiochemical methods and wet chemical techniques for major components, minor components and radionuclides.  
1.2 One of the fusion practices and the microwave practice can be used in hot cells and shielded hoods after modification to meet local operational requirements.  
1.3 The user of these practices must follow radiation protection guidelines in place for their specific laboratories.  
1.4 Additional information relating to safety is included in the text.  
1.5 The dissolution techniques described in these practices can be used for quality control of the feed materials and the product of plants vitrifying nuclear waste materials in glass.  
1.6 These practices are introduced to provide the user with an alternative means to Test Methods C169 for dissolution of waste containing glass in shielded facilities. Test Methods C169 is not practical for use in such facilities and with radioactive materials.  
1.7 The ICP-AES methods in Test Methods C1109 and C1111 can be used to analyze the dissolved sample with additional sample preparation as necessary and with matrix effect considerations. Additional information as to other analytical methods can be found in Test Method C169.  
1.8 Solutions from this practice may be suitable for analysis using ICP-MS after establishing laboratory performance criteria and verification that the criteria can be met. For example, Test Methods C1287 or C1637 may be used with additional sample preparation as necessary and appropriate matrix effect considerations.  
1.9 The values stated in SI units are to be regarded as standard. Units in parentheses are for information only.  
1.10 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. Specific precautionary statements are given in Sections 10, 20, and 30.  
1.11 This international standard was developed in accordance with internationally recognized principles on standardization established in the De...

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ASTM
ASTM C1718-10(2019)(Test Method)
Standard Test Method for Nondestructive Assay of Radioactive Material by Tomographic Gamma Scanning

SIGNIFICANCE AND USE
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.  
5.5 In determining the radionuclide distribution inside an item, the TGS analysis explicitly takes into account the cross talk between various vertical layers of the item.  
5.6 The TGS analysis technique uses a material basis set method that does not require the user to select a mass attenuation curve apriori, provided the transmission source has at least 2 gamma lines that span the energy range of interest.  
5.7 A commercially available TGS system consists of building blocks that can easily be configured to operate the system in the ...
SCOPE
1.1 This test method describes the nondestructive assay (NDA) of gamma ray emitting radionuclides inside containers using tomographic gamma scanning (TGS). High resolution gamma ray spectroscopy is used to detect and quantify the radionuclides of interest. The attenuation of an external gamma ray transmission source is used to correct the measurement of the emission gamma rays from radionuclides to arrive at a quantitative determination of the radionuclides present in the item.  
1.2 The TGS technique covered by the test method may be used to assay scrap or waste material in cans or drums in the 1 to 500 litre volume range. Other items may be assayed as well.  
1.3 The test method will cover two implementations of the TGS procedure: (1) Isotope Specific Calibration that uses standards of known radionuclide masses (or activities) to determine system response in a mass (or activity) versus corrected count rate calibration, that applies to only those specific radionuclides for which it is calibrated, and (2) Response Curve Calibration that uses gamma ray standards to determine system response as a function of gamma ray energy and thereby establishes calibration for all gamma emitting radionuclides of interest.  
1.4 This test method will also include a technique to extend the range of calibration above and below the extremes of the measured calibration data.  
1.5 The assay technique covered by the test method is applicable to a wide range of item sizes, and for a wide range of matrix attenuation. The matrix attenuation is a function of the matrix composition, photon energy, and the matrix density. The matrix types that can be assayed range from light combustibles to cemented sludge or concrete. It is particularly well suited for items that have heterogeneous matrix material and non-uniform radioisotope distributions. Measured transmission values should be available to permit valid attenuation corrections, but are not n...

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ASTM C1133/C1133M-10(2018)(Test Method)
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
5.1 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.  
5.2 The procedure can serve as a diagnostic tool that provides a vertical profile of transmission and nuclide concentration within the item.  
5.3 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.  
5.4 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).2  
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 esta...

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