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ASTM C1913-21

(Practice)

Standard Practice for Sampling Gaseous Uranium Hexafluoride Using Zeolite in Single-Use Destructive Assay Sampler

Standard Practice for Sampling Gaseous Uranium Hexafluoride Using Zeolite in Single-Use Destructive Assay Sampler

SIGNIFICANCE AND USE
5.1 Facility operators and safeguards inspectors routinely collect UF6 samples from processing lines, isotopic enrichment cascades or storage cylinders to determine uranium isotopic composition. The isotope ratio n(235U)/n(238U) is particularly important since it is used to calculate the amount of fissile 235U in the sample.  
5.2 Conventional sampling practices (such as Practices C1052 and C1703) collect samples of UF6, usually in quantities greater than one gram. Due to the chemical hazards of UF6 (and in some cases the high collection mass), an increasing number of air transport operators are unwilling to transport such samples. In contrast, SUDA samples are expected to be transported as excepted quantities (for example, under UN 2910 (3)), as the conversion to a less hazardous, more stable chemical species avoids the chemical hazards of UF6 similar to Practice C1880. Additionally, the decreased shipping requirement and small collection mass of SUDA samplers (less than Practice C1880) allow for multiple SUDA samples to be transported in the same shipment.  
5.3 For safeguards applications, isotopic measurements that fall within the 2010 International Target Value (ITV) ranges (5) have been demonstrated (1).  
5.4 This practice provides the following qualities:  
5.4.1 Fitness for purpose in verifying nuclear material declarations.  
5.4.2 A safe, simple and fast procedure for the sample collector that minimizes sample handling and potential for cross-contamination.  
5.4.3 Flexibility for use in a wide variety of facilities.  
5.4.4 Robustness to adapt to minor changes in facility operating parameters.  
5.4.5 Confidentiality for the operating facility from which the sample is collected.  
5.4.6 Safety in sample handling and transport since the sample is a less hazardous, more stable form (specifically, UO2F2 is more stable and less volatile than UF6 gas).  
5.4.7 Ease of sample preparation in the laboratory with reduced processing hazards during recove...
SCOPE
1.1 This practice is applicable to sampling gaseous uranium hexafluoride (UF6) from processing facilities, isotope enrichment cascades or storage cylinders, using the sorbent properties of zeolite in a single-use destructive assay (SUDA) sampler.  
1.2 This practice is based on the SUDA method developed at Pacific Northwest National Laboratory (1)2 for collection of samples of UF6 for determination of uranium isotopic content for nuclear material safeguards and other applications.  
1.3 The UF6 collected is converted to uranyl fluoride (UO2F2), allowing samples to be handled and categorized for transport under less stringent conditions than are required for UF6.  
1.4 This practice can be used to collect samples for safeguards measurements. Safeguards samples collected with this practice have been shown to provide suitable isotopic measurements (1).  
1.5 This practice has not been demonstrated for suitability for compliance with Specifications C787 and C996. Practices C1052 or C1703 can be used to collect samples for compliance with these specifications.  
1.6 The scope of this practice does not include provisions for preventing criticality.  
1.7 Units—The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered standard.  
1.8 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.  
1.9 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 Bar...

General Information

Status
Published
Publication Date
31-May-2021
ICS
27.120.30 - Fissile materials and nuclear fuel technology
Technical Committee
C26 - Nuclear Fuel Cycle
Drafting Committee
C26.02 - Fuel and Fertile Material Specifications
Current Stage
Ref Project

Relations

Refers
ASTM C787-20 - Standard Specification for Uranium Hexafluoride for Enrichment
Effective Date
01-Mar-2020
Refers
ASTM C996-20 - Standard Specification for Uranium Hexafluoride Enriched to Less Than 5&#x2009;%&#x2009;<sup > 235</sup>U
Effective Date
01-Mar-2020
Refers
ASTM C1052-20 - Standard Practice for Bulk Sampling of Liquid Uranium Hexafluoride
Effective Date
01-Jul-2020

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ASTM C1913-21 - Standard Practice for Sampling Gaseous Uranium Hexafluoride Using Zeolite in Single-Use Destructive Assay SamplerASTM C1913-21 - Standard Practice for Sampling Gaseous Uranium Hexafluoride Using Zeolite in Single-Use Destructive Assay Sampler
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ASTM C1913-21 - Standard Practice for Sampling Gaseous Uranium Hexafluoride Using Zeolite in Single-Use Destructive Assay Sampler
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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:C1913 −21
Standard Practice for
Sampling Gaseous Uranium Hexafluoride Using Zeolite in
1
Single-Use Destructive Assay Sampler
This standard is issued under the fixed designation C1913; 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 1.9 This international standard was developed in accor-
dance with internationally recognized principles on standard-
1.1 This practice is applicable to sampling gaseous uranium
ization established in the Decision on Principles for the
hexafluoride (UF ) from processing facilities, isotope enrich-
6
Development of International Standards, Guides and Recom-
ment cascades or storage cylinders, using the sorbent proper-
mendations issued by the World Trade Organization Technical
ties of zeolite in a single-use destructive assay (SUDA)
Barriers to Trade (TBT) Committee.
sampler.
1.2 This practice is based on the SUDA method developed 2. Referenced Documents
2
at Pacific Northwest National Laboratory (1) for collection of 3
2.1 ASTM Standards:
samples of UF for determination of uranium isotopic content
6
C787 Specification for Uranium Hexafluoride for Enrich-
for nuclear material safeguards and other applications.
ment
1.3 The UF collected is converted to uranyl fluoride C859 Terminology Relating to Nuclear Materials
6
(UO F ), allowing samples to be handled and categorized for C996 Specification for Uranium Hexafluoride Enriched to
2 2
235
transport under less stringent conditions than are required for Less Than 5 % U
UF . C1052 Practice for Bulk Sampling of Liquid Uranium
6
Hexafluoride
1.4 This practice can be used to collect samples for safe-
C1474 Test Method forAnalysis of Isotopic Composition of
guards measurements. Safeguards samples collected with this
Uranium in Nuclear-Grade Fuel Material by Quadrupole
practicehavebeenshowntoprovidesuitableisotopicmeasure-
Inductively Coupled Plasma-Mass Spectrometry
ments (1).
C1477 Test Method for Isotopic Abundance Analysis of
1.5 This practice has not been demonstrated for suitability
Uranium Hexafluoride and Uranyl Nitrate Solutions by
for compliance with Specifications C787 and C996. Practices
Multi-Collector, Inductively Coupled Plasma-Mass Spec-
C1052 or C1703 can be used to collect samples for compliance
trometry
with these specifications.
C1672 Test Method for Determination of Uranium or Pluto-
nium Isotopic Composition or Concentration by the Total
1.6 The scope of this practice does not include provisions
Evaporation Method Using a Thermal Ionization Mass
for preventing criticality.
Spectrometer
1.7 Units—The values stated in SI units are to be regarded
C1703 Practice for Sampling of Gaseous Uranium
as standard. The values given in parentheses after SI units are
Hexafluoride for Enrichment
provided for information only and are not considered standard.
C1832 Test Method for Determination of Uranium Isotopic
1.8 This standard does not purport to address all of the
Composition by Modified Total Evaporation (MTE)
safety concerns, if any, associated with its use. It is the
Method Using Thermal Ionization Mass Spectrometer
responsibility of the user of this standard to establish appro-
C1871 Test Method for Determination of Uranium Isotopic
priate safety, health, and environmental practices and deter-
Composition by the Double Spike Method Using a Ther-
mine the applicability of regulatory limitations prior to use.
mal Ionization Mass Spectrometer
C1880 Practice for Sampling Gaseous Uranium Hexafluo-
ride using Alumina Pellets
1
D1193 Specification for Reagent Water
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.02 on Fuel and
Fertile Material Specifications.
3
Current edition approved June 1, 2021. Published July 2021. DOI: 10.1520/ For referenced ASTM standards, visit the ASTM website, www.astm.org, or
C1913-21. 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

---------------------- Page: 1 ----------------------
C1913−21
FIG. 1Exploded View of SUDA Sampler
D1418 Practice for Rubber and Rubber Latices— 4.2 At the end of the sampling period
...

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5.1 Uranium hexafluoride is a basic material used to produce nuclear reactor fuel. To be suitable for this purpose, the material must meet criteria for isotopic composition. This test method is designed to determine whether the material meets the requirements described in Specifications C787 and C996.
SCOPE
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SCOPE
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1.1 This terminology standard contains terms, definitions, descriptions of terms, nomenclature, and explanations of acronyms and symbols specifically associated with standards under the jurisdiction of Committee C26 on Nuclear Fuel Cycle. The content of this terminology standard may also be applicable to documents not under the jurisdiction of Committee C26, in which case this terminology standard may be referenced in those documents.  
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SCOPE
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SCOPE
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Standard Guide for Preparation of Working Reference Materials for Use in Analysis of Nuclear Fuel Cycle Materials

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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  
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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...
SCOPE
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.  
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1.6...

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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.  
5.3 A chemical calibration of the coulometer is necessary for accurate results.
FIG. 1 Example of a Cell Design Used at Los Alamos National Laboratory (LANL)
SCOPE
1.1 This test method covers the determination of milligram quantities of plutonium in unirradiated uranium-plutonium mixed oxide having a U/Pu ratio range of 0.1 to 10. This test method is also applicable to plutonium metal, plutonium oxide, uranium-plutonium mixed carbide, various plutonium compounds including fluoride and chloride salts, and plutonium solutions.  
1.2 The recommended amount of plutonium for each aliquant in the coulometric analysis is 5 mg to 10 mg. Precision worsens for lower amounts of plutonium, and elapsed time of electrolysis becomes impractical for higher amounts of plutonium.  
1.3 The quantity values stated in SI units are to be regarded as standard. The quantity values with non-SI units are given in parentheses 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. Specific precautionary statements are given in Section 9.  
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 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.
SCOPE
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 C1490-14(2023)(Guide)
Standard Guide for the Selection, Training and Qualification of Nondestructive Assay (NDA) Personnel

SIGNIFICANCE AND USE
4.1 The process of selection, training and qualification of personnel involved with NDA measurements is one of the quality assurance elements for an overall quality NDA measurement program.  
4.2 This guide describes an approach to selection, qualification, and training of personnel that is to be used in conjunction with other NDA Quality Assurance (QA) program elements. The selection, qualification and training processes can vary and this guide provides one such approach.  
4.3 The qualification activities described in this guide assume that NDA personnel are already proficient in general facility operations and safety procedures. The training and activities that developed this proficiency are not covered in this guide.  
4.4 This guide describes a basic approach and principles for the qualification of NDA professionals and technical specialists and operators. A different approach may be adopted by the management organization based on its particular organization and facility specifics. However, if a variation of the approach of this guide is applied, the resulting selection, training, and qualification programs must meet the requirements of the facility quality assurance program and should provide all the applicable functions of Section 5.  
4.5 This guide may be used as an aid in the preparation of a Training Implementation Plan (TIP) for the Transuranic Waste Characterization Program (TWCP).  
4.6 This guide describes education and expertise guidance for NDA auditors due to the importance and complexity of proper oversight of NDA activities.
SCOPE
1.1 This guide contains good practices for the selection, training, qualification, and professional development of personnel performing analysis, calibration, physical measurements, or data review using nondestructive assay equipment, methods, results, or techniques. The guide also covers NDA personnel involved with NDA equipment setup, selection, diagnosis, troubleshooting, or repair. General guidelines for the selection, training, and qualification of NDA auditors are included as well, but at a lower level of detail due to the variability of the personnel’s responsibilities performing this functions. Selection, training, and qualification programs based on this guide are intended to provide assurance that NDA personnel are suitably qualified and experienced personnel (SQEP) to perform their jobs competently. This guide presents a series of options but does not recommend a specific course of action.
This standard guide does not address the qualifications per se of an NDA Manager. However, it is expected that the NDA Manager is familiar with NDA techniques, and can make informed decisions on the acceptability of the assay results. If an NDA Manager does not have adequate technical qualifications in the NDA field, they are recommended to undergo training to gain familiarity in this area.
An NDA Manager with no relevant NDA experience should have access to a Senior NDA Professional who will give guidance for all technical decisions such as applicability and limitation of methods, reasonableness of results, needed upgrades and advantageous development investments.  
1.2 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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