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ASTM C1493-19

(Test Method)

Standard Test Method for Non-Destructive Assay of Nuclear Material in Waste by Passive and Active Neutron Counting Using a Differential Die-Away System

Standard Test Method for Non-Destructive Assay of Nuclear Material in Waste by Passive and Active Neutron Counting Using a Differential Die-Away System

SIGNIFICANCE AND USE
5.1 This test method is useful for quantifying fissile (for example, 233U, 235U,  239Pu and 241Pu) and spontaneously-fissioning nuclei (for example, 238Pu, 240Pu,  242Pu, 244Cm,
248Cm, and  252Cf) in waste and scrap drums. Total elemental mass of the radioactive materials can be calculated if the relative abundances of each radionuclide are known.  
5.1.1 Typically, this test method is used to measure one fissile isotope (for example, 235U or  239Pu).  
5.2 This test method can be used to segregate low level and transuranic waste at the 100 nCi/g concentration level currently required to meet the DOE Waste Isolation Pilot Plant (WIPP) waste acceptance criterion (5, 8, 9).  
5.3 This test method can be used for waste characterization to demonstrate compliance with the radioactivity levels specified in waste, disposal, and environmental regulations (See NRC regulatory guides, DOE Order 435.1, 10 CFR Part 71, 40 CFR Part 191, and DOE /WIPP-069).  
5.3.1 In the active mode, the DDT system can measure the 235U content in the range from 100 g and the 239Pu content, nominally between 20 g.  
5.3.2 In the passive mode, the DDT system is capable of assaying spontaneously-fissioning nuclei, over a nominal range from 0.05 to 15 g of 240Pu, or equivalent (5, 10, 11, 12, 13).  
5.4 This test method should be used in conjunction with a waste management plan that segregates the contents of assay items into material categories according to some or all of the following criteria: bulk density of the waste, chemical forms of the plutonium or uranium and matrix, (α, n) neutron intensity, hydrogen (moderator) and absorber content, thickness of fissile mass(es), and the assay item container size and composition. Each matrix may require a different set of calibration standards and may have different mass calibration limits. The effect on the quality of the assay (that is, minimizing precision and bias) can significantly depend on the degree of adherence to this waste management pl...
SCOPE
1.1 This test method covers a system that performs nondestructive assay (NDA) of uranium or plutonium, or both, using the active, differential die-away technique (DDT), and passive neutron coincidence counting. Results from the active and passive measurements are combined to determine the total amount of fissile and spontaneously-fissioning material in drums of scrap or waste. Corrections are made to the measurements for the effects of neutron moderation and absorption, assuming that the effects are averaged over the volume of the drum and that no significant lumps of nuclear material are present. These systems are most widely used to assay low-level and transuranic waste, but may also be used for the measurement of scrap materials. The examples given within this test method are specific to the second-generation Los Alamos National Laboratory (LANL) passive-active neutron assay system.  
1.1.1 In the active mode, the system measures fissile isotopes such as 235U and 239Pu. The neutrons from a pulsed, 14-MeV neutron generator are thermalized to induce fission in the assay item. Between generator pulses, the system detects prompt-fission neutrons emitted from the fissile material. The number of detected neutrons between pulses is proportional to the mass of fissile material. This method is called the differential die-away technique.  
1.1.2 In the passive mode, the system detects time-coincident neutrons emitted from spontaneously fissioning isotopes. The primary isotopes measured are 238Pu, 240 Pu, and 242Pu; however, the system may be adapted for use on other spontaneously-fissioning isotopes as well, such as kilogram quantities of 238U. The number of coincident neutrons detected is proportional to the mass of spontaneously-fissioning material.  
1.2 The active mode is used to assay fissile material in the following ranges.  
1.2.1 For uranium-only bearing items, the DDT can measure the 235U content in the range from...

General Information

Status
Published
Publication Date
14-Mar-2019
ICS
27.120.30 - Fissile materials and nuclear fuel technology
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.10 - Non Destructive Assay
Current Stage
Ref Project

Relations

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
Refers
ASTM C1215-18 - Standard Guide for Preparing and Interpreting Precision and Bias Statements in Test Method Standards Used in the Nuclear Industry
Effective Date
01-Jul-2018
Referred By
ASTM C1490-14(2023) - Standard Guide for the Selection, Training and Qualification of Nondestructive Assay (NDA) Personnel
Effective Date
15-Mar-2019
Referred By
ASTM C1592/C1592M-21 - Standard Guide for Making Quality Nondestructive Assay Measurements
Effective Date
15-Mar-2019

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ASTM C1493-19 - Standard Test Method for Non-Destructive Assay of Nuclear Material in Waste by Passive and Active Neutron Counting Using a Differential Die-Away SystemASTM C1493-19 - Standard Test Method for Non-Destructive Assay of Nuclear Material in Waste by Passive and Active Neutron Counting Using a Differential Die-Away System
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ASTM C1493-19 - Standard Test Method for Non-Destructive Assay of Nuclear Material in Waste by Passive and Active Neutron Counting Using a Differential Die-Away System
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Standards Content (Sample)

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: C1493 − 19
Standard Test Method for
Non-Destructive Assay of Nuclear Material in Waste by
Passive and Active Neutron Counting Using a Differential
1
Die-Away System
This standard is issued under the fixed designation C1493; the number immediately following the designation indicates the year 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 For uranium-only bearing items, the DDT can mea-
235
sure the U content in the range from about 0.02 to over 100
1.1 This test method covers a system that performs nonde-
g. Small mass uranium-bearing items are typically measured
structiveassay(NDA)ofuraniumorplutonium,orboth,using
using the active mode and only large mass items are measured
the active, differential die-away technique (DDT), and passive
in passive mode.
neutron coincidence counting. Results from the active and
1.2.2 For plutonium-only bearing items, the DDT method
passive measurements are combined to determine the total
239
measures the Pu content in the range between about 0.01
amount of fissile and spontaneously-fissioning material in
and 20 g.
drums of scrap or waste. Corrections are made to the measure-
ments for the effects of neutron moderation and absorption,
1.3 Thepassivemodeiscapableofassayingspontaneously-
240
assuming that the effects are averaged over the volume of the
fissioningnuclei,overanominalrangefrom0.05to15g Pu
drum and that no significant lumps of nuclear material are
equivalent.
present.Thesesystemsaremostwidelyusedtoassaylow-level
1.4 This test method requires knowledge of the relative
and transuranic waste, but may also be used for the measure-
abundances of the plutonium or uranium isotopes to determine
ment of scrap materials. The examples given within this test
the total plutonium or uranium mass.
method are specific to the second-generation Los Alamos
National Laboratory (LANL) passive-active neutron assay
1.5 Thistestmethodwillgivebiasedresultswhenthewaste
system.
form does not meet the calibration specifications and the
1.1.1 In the active mode, the system measures fissile iso-
measurementassumptionspresentedinthistestmethodregard-
235 239
topes such as U and Pu. The neutrons from a pulsed,
ing the requirements for a homogeneous matrix, uniform
14-MeVneutron generator are thermalized to induce fission in
source distribution, and the absence of nuclear material lumps,
the assay item. Between generator pulses, the system detects
to the extent that they effect the measurement.
prompt-fission neutrons emitted from the fissile material. The
1.6 The complete active and passive assay of a 208 Ldrum
number of detected neutrons between pulses is proportional to
isnominally10minorlessbuteithermodecanbeextendedto
the mass of fissile material. This method is called the differ-
meet data quality objectives.
ential die-away technique.
1.1.2 In the passive mode, the system detects time-
1.7 Some improvements to this test method have been
2
coincident neutrons emitted from spontaneously fissioning
reported (1, 2, 3, 4). Discussions of these improvements are
238 240
isotopes. The primary isotopes measured are Pu, Pu,
not included in this test method although improvements
242
and Pu; however, the system may be adapted for use on
continue to occur.
other spontaneously-fissioning isotopes as well, such as kilo-
238 1.8 The values stated in SI units are to be regarded as
gram quantities of U. The number of coincident neutrons
standard. No other units of measurement are included in this
detected is proportional to the mass of spontaneously-
standard.
fissioning material.
1.9 This standard may involve hazardous materials,
1.2 The active mode is used to assay fissile material in the
operations, and equipment. This standard does not purport to
following ranges.
address all of the safety concerns, if any, associated with its
use. It is the responsibility of the user of this standard to
1
ThistestmethodisunderthejurisdictionofASTMCommitteeC26onNuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.10 on Non
Destructive Assay.
Current edition approved March 15, 2019. Published April 2019. Originally
2
approvedin2001.Lastpreviouseditionapprovedin2009asC1493–09,whichwas The boldface numbers given in parentheses refer to a list of references at the
withdrawn January 2018 and reinstated in March 2019. DOI: 10.1520/C1493-19. end of the text.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

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This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. The diversity of manufacturing methods shall be recognized by which uranium-plutonium dioxide pellets are produced and the many special requirements for chemical and physical characterization that may be imposed by the operating conditions to which the pellets will be subjected in specific reactor systems. The following are different chemical requirements that shall be determined: uranium content, plutonium content, impurity content, stoichiometry, moisture content, gas content, and americium-241 content. Nuclear requirements such as isotopic content, plutonium equivalent at a given date, equivalent boron content, and reactivity shall also be determined. Physical properties of the pellets like dimensions, density, grain size, pore morphology, plutonium-oxide homogeneity, plutonium-oxide particle size, plutonium-oxide particle distribution, integrity, and surface cracks shall be determined as well. The surfaces of finished pellets shall be visually free of loose chips, oil, macroscopic inclusions, and foreign materials. An estimate of the fuel pellet irradiation stability shall be obtained unless adequate allowance for such effects are factored into the fuel rod design. The estimate of the stability shall consist of either conformance to the thermal stability test as specified in the or by adequate correlation of manufacturing process or microstructure to in-reactor behavior, or both.
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4.1 Factors governing selection of a method for the determination of uranium include available quantity of sample, sample purity, desired level of reliability, and equipment availability.  
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5.5 Holdup Monitoring—Periodic re-measurement of holdup at a defined point using the same technique and a...
SCOPE
1.1 This test method describes gamma-ray methods used to nondestructively measure the quantity of 235U or  239Pu present as holdup in nuclear facilities. Holdup may occur in any facility where nuclear material is processed, in process equipment, in exhaust ventilation systems and in building walls and floors.  
1.2 This test method includes information useful for management, planning, selection of equipment, consideration of interferences, measurement program definition, and the utilization of resources  (1, 2, 3, 4) .2  
1.3 The measurement of nuclear material hold up in process equipment requires a scientific knowledge of radiation sources and detectors, transmission of radiation, calibration, facility operations and uncertainty analysis. It is subject to the constraints of the facility, management, budget, and schedule; plus health and safety requirements. The measurement process includes defining measurement uncertainties and is sensitive to the form and distribution of the material, various backgrounds, and interferences. The work includes investigation of material distributions within a facility, which could include potentially large holdup surface areas. Nuclear material held up in pipes, ductwork, gloveboxes, and heavy equipment, is usually distributed in a diffuse and irregular manner. It is difficult to define the measurement geometry, to identify the form of the material, and to measure it without interference from adjacent sources of radiation.  
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...

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ASTM
ASTM C1108-23(Test Method)
Standard Test Method for Plutonium by Controlled-Potential Coulometry

SIGNIFICANCE AND USE
5.1 Factors governing selection of a method for the determination of plutonium include available quantity of sample, sample purity, desired level of reliability, and equipment.  
5.1.1 This test method determines 5 mg to 20 mg of plutonium with prior dissolution using Practice C1168.  
5.1.2 This test method calculates plutonium mass fraction in solutions and solids using an electrical calibration based upon Ohm’s Law and the Faraday Constant.  
5.1.3 Chemical standards are used for quality control. When prior chemical separation of plutonium is necessary to remove interferences, the quality control standards should be included with each chemical separation batch (9).  
5.2 Fitness for Purpose of Safeguards and Nuclear Safety Application—Methods intended for use in safeguards and nuclear safety applications shall meet the requirements specified by Guide C1068 for use in such applications.
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1.1 This test method describes the determination of dissolved plutonium from unirradiated nuclear-grade (that is, high-purity) materials by controlled-potential coulometry. Controlled-potential coulometry may be performed in a choice of supporting electrolytes, such as 0.9 mol/L (0.9 M) HNO3, 1 mol/L (1 M) HClO4, 1 mol/L (1 M) HCl, 5 mol/L (5 M) HCl, and 0.5 mol/L (0.5 M) H2SO4. Limitations on the use of selected supporting electrolytes are discussed in Section 6. Optimum quantities of plutonium for this procedure are 5 mg to 20 mg.  
1.2 Plutonium-bearing materials are radioactive and toxic. Adequate laboratory facilities, such as gloved boxes, fume hoods, controlled ventilation, etc., along with safe techniques must be used in handling specimens containing these materials.  
1.3 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.4 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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ASTM
ASTM C1128-23(Guide)
Standard Guide for Preparation of Working Reference Materials for Use in Analysis of Nuclear Fuel Cycle Materials

SIGNIFICANCE AND USE
5.1 Certified reference materials (CRMs) prepared from nuclear materials are well characterized, traceable, and sufficiently homogenous and stable for their intended use. Usually they are certified using the most unbiased and precise measurement methods available, often with more than one laboratory being used on a national or international level. CRMs are at the top of the metrological hierarchy of reference materials. A graphical representation of a typical national nuclear measurement system is shown in Fig. 3.
FIG. 3 Typical National Nuclear Measurement System  
5.2 Working reference materials (WRMs) need to have quality characteristics that are similar to CRMs, although the rigor used to achieve those characteristics is not usually as stringent as for CRMs. Similarly, production of WRMs should be in accordance with applicable requirements of ISO 17034. Where possible, CRMs are typically used to calibrate the methods used for establishing reference values assigned to WRMs, thus providing traceability to CRMs as required by ISO/IEC 17025. A WRM is normally prepared for a specific application.  
5.3 Because of the importance of having highly reliable measurement data from nuclear material analysis, particularly for material control and accountability purposes, CRMs are used for calibration when available. However, CRMs prepared from nuclear materials are not always available for specific applications. Thus, there may be a need for a laboratory to prepare nuclear material WRMs to meet specific needs; for example, to match the matrix in process samples. In such cases, a WRM can be tailored to meet specific needs of a process or laboratory. Also, CRM supply may be too limited for use in the quantities needed for long-term, routine use. When properly prepared, WRMs will serve equally well as CRMs for most applications, and using WRMs will help preserve supplies of CRMs.  
5.4 Difficulties may be encountered in the preparation of RMs from nuclear materials becaus...
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1.1 This guide covers the preparation and characterization of working reference materials (WRM) that are produced by a laboratory for its own use in the analysis of nuclear fuel cycle materials. Guidance is provided for proper planning, preparation, packaging, and storage; requirements for characterization; homogeneity and stability considerations; and value assignment. When traceability to SI is desired for a WRM, it will be achieved by a defined, statistically sound characterization process that is traceable to a certified value on a certified reference materials. While the guidance provided is generic for nuclear fuel cycle materials, detailed examples for some materials are provided in the appendixes.  
1.2 This guide does not apply to the production and characterization of certified reference materials (CRM). Refer to ISO 17034 and ISO Guide 35 for guidance on reference material production, characterization, certification, sale, and distribution requirements.  
1.3 The information provided by this guide is found in the following sections:    
Section  
Perform WRM Planning  
6  
Prepare and Process Materials  
7  
Packaging and Storage of Materials  
8  
Perform Homogeneity Study  
9  
Perform Stability Studies  
10  
Characterize Materials  
11  
Perform Uncertainty Analysis  
12  
Produce Documentation  
13  
Carry Out WRM Utilization and Monitoring  
14  
1.4 The values stated in SI units are to be regarded as standard. The non-SI units of molar, M, and normal, N, are also regarded as standard. Any non-SI units of measurement shown in parentheses are for information only.  
1.5 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.  
1.6...

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