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ASTM C1500-08(2017)

(Test Method)

Standard Test Method for Nondestructive Assay of Plutonium by Passive Neutron Multiplicity Counting

Standard Test Method for Nondestructive Assay of Plutonium by Passive Neutron Multiplicity Counting

SIGNIFICANCE AND USE
5.1 This test method is useful for determining the plutonium content of items such as impure Pu oxide, mixed Pu/U oxide, oxidized Pu metal, Pu scrap and waste, Pu process residues, and weapons components.  
5.2 Measurements made with this test method may be suitable for safeguards or waste characterization requirements such as:  
5.2.1 Nuclear materials accountability,  
5.2.2 Inventory verification (7),  
5.2.3 Confirmation of nuclear materials content (8),  
5.2.4 Resolution of shipper/receiver differences (9),  
5.2.5 Excess weapons materials inspections  (10, 11),  
5.2.6 Safeguards termination on waste  (12, 13),  
5.2.7 Determination of fissile equivalent content (14).  
5.3 A significant feature of neutron multiplicity counting is its ability to capture more information than neutron coincidence counting because of the availability of a third measured parameter, leading to reduced measurement bias for most material categories for which suitable precision can be attained. This feature also makes it possible to assay some in-plant materials that are not amenable to conventional coincidence counting, including moist or impure plutonium oxide, oxidized metal, and some categories of scrap, waste, and residues (10).  
5.4 Calibration for many material types does not require representative standards. Thus, the technique can be used for inventory verification without calibration standards (7), although measurement bias may be lower if representative standards were available.  
5.4.1 The repeatability of the measurement results due to counting statistics is related to the quantity of nuclear material, interfering neutrons, and the count time of the measurement (15) .  
5.4.2 For certain materials such as small Pu, items of less than 1 g, some Pu-bearing waste, or very impure Pu process residues where the (α,n) reaction rate overwhelms the triples signal, multiplicity information may not be useful because of the poor counting statistics of the triple coinci...
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1.1 This test method describes the nondestructive assay of plutonium in forms such as metal, oxide, scrap, residue, or waste using passive neutron multiplicity counting. This test method provides results that are usually more accurate than conventional neutron coincidence counting. The method can be applied to a large variety of plutonium items in various containers including cans, 208-L drums, or 1900-L Standard Waste Boxes. It has been used to assay items whose plutonium content ranges from 1 g to 1000s of g.  
1.2 There are several electronics or mathematical approaches available for multiplicity analysis, including the multiplicity shift register, the Euratom Time Correlation Analyzer, and the List Mode Module, as described briefly in Ref. (1).2  
1.3 This test method is primarily intended to address the assay of 240Pu-effective by moments-based multiplicity analysis using shift register electronics (1, 2, 3) and high efficiency neutron counters specifically designed for multiplicity analysis.  
1.4 This test method requires knowledge of the relative abundances of the plutonium isotopes to determine the total plutonium mass (See Test Method C1030).  
1.5 This test method may also be applied to modified neutron coincidence counters (4) which were not specifically designed as multiplicity counters (that is, HLNCC, AWCC, etc), with a corresponding degradation of results.  
1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this 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.

General Information

Status
Published
Publication Date
31-Dec-2016
ICS
13.030.30 - Special wastes
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.10 - Non Destructive Assay
Current Stage
Ref Project

Relations

Refers
ASTM C1458-16 - Standard Test Method for Nondestructive Assay of Plutonium, Tritium and&#x2009;<sup >241</sup>Am by Calorimetric Assay
Effective Date
01-Mar-2016
Refers
ASTM C1030-10(2018) - Standard Test Method for Determination of Plutonium Isotopic Composition by Gamma-Ray Spectrometry
Effective Date
01-Apr-2018
Refers
ASTM C1207-10(2018) - Standard Test Method for Nondestructive Assay of Plutonium in Scrap and Waste by Passive Neutron Coincidence Counting
Effective Date
01-Apr-2018
Refers
ASTM C1673-10a(2018) - Standard Terminology of C26.10 Nondestructive Assay Methods
Effective Date
01-Apr-2018

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ASTM C1500-08(2017) - Standard Test Method for Nondestructive Assay of Plutonium by Passive Neutron Multiplicity CountingASTM C1500-08(2017) - Standard Test Method for Nondestructive Assay of Plutonium by Passive Neutron Multiplicity Counting
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ASTM C1500-08(2017) - Standard Test Method for Nondestructive Assay of Plutonium by Passive Neutron Multiplicity Counting
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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.
Designation: C1500 − 08 (Reapproved 2017)
Standard Test Method for
Nondestructive Assay of Plutonium by Passive Neutron
1
Multiplicity Counting
This standard is issued under the fixed designation C1500; 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 priate safety, health, and environmental practices and deter-
mine the applicability of regulatory limitations prior to use.
1.1 This test method describes the nondestructive assay of
plutonium in forms such as metal, oxide, scrap, residue, or
2. Referenced Documents
waste using passive neutron multiplicity counting. This test
3
2.1 ASTM Standards:
method provides results that are usually more accurate than
C1030 Test Method for Determination of Plutonium Isotopic
conventional neutron coincidence counting. The method can be
Composition by Gamma-Ray Spectrometry
applied to a large variety of plutonium items in various
C1207 Test Method for Nondestructive Assay of Plutonium
containers including cans, 208-L drums, or 1900-L Standard
in Scrap and Waste by Passive Neutron Coincidence
Waste Boxes. It has been used to assay items whose plutonium
Counting
content ranges from 1 g to 1000s of g.
C1458 Test Method for Nondestructive Assay of Plutonium,
1.2 There are several electronics or mathematical ap- 241
Tritium and Am by Calorimetric Assay
proaches available for multiplicity analysis, including the
C1490 Guide for the Selection, Training and Qualification of
multiplicity shift register, the Euratom Time Correlation
Nondestructive Assay (NDA) Personnel
Analyzer, and the List Mode Module, as described briefly in
C1592 Guide for Making Quality Nondestructive Assay
2
Ref. (1).
Measurements
1.3 This test method is primarily intended to address the C1673 Terminology of C26.10 Nondestructive Assay Meth-
240
assay of Pu-effective by moments-based multiplicity analy- ods
sis using shift register electronics (1, 2, 3) and high efficiency
3. Terminology
neutron counters specifically designed for multiplicity analysis.
3.1 Definitions:
1.4 This test method requires knowledge of the relative
3.1.1 Terms shall be defined in accordance with Terminol-
abundances of the plutonium isotopes to determine the total
ogy C1673 except for the following:
plutonium mass (See Test Method C1030).
3.1.2 gate fractions, n—the fraction of the total coincidence
1.5 This test method may also be applied to modified
events that occur within the coincidence gate.
neutron coincidence counters (4) which were not specifically
3.1.2.1 doubles gate fraction (f ), n—the fraction of the
d
designed as multiplicity counters (that is, HLNCC, AWCC,
theoretical double coincidences that can be detected within the
etc), with a corresponding degradation of results.
coincidence gate (see Eq 1).
1.6 The values stated in SI units are to be regarded as
3.1.2.2 triples gate fraction (f ), n—the fraction of the
t
standard. No other units of measurement are included in this
theoretical triple coincidences that can be detected within the
standard.
coincidence gate (see Eq 2).
1.7 This standard does not purport to address all of the
3.1.3 factorial moment of order, n—this is a derived quantity
safety concerns, if any, associated with its use. It is the
calculated by summing the neutron multiplicity distribution
responsibility of the user of this standard to establish appro-
weighted by ν!/(ν – n)! where n is the order of the moment.
3.1.4 induced fission neutron multiplicities (ν , ν , ν ),
i1 i2 i3
n—the factorial moments of the induced fission neutron mul-
1
This test method is under the jurisdiction of ASTM Committee C26 on Nuclear
tiplicity distribution. Typically multiplicity analysis will utilize
Fuel Cycle and is the direct responsibility of Subcommittee C26.10 on Non
Destructive Assay.
Current edition approved Jan. 1, 2017. Published January 2017. Originally
3
approved in 2002. Last previous edition approved in 2008 as C1500 – 08. DOI: For referenced ASTM standards, visit the ASTM website, www.astm.org, or
10.1520/C1500-08R17. contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
2
The boldface numbers in parentheses refer to the list of references at the end of Standards volume information, refer to the standard’s Document Summary page on
this standard. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

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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 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
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 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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