ASTM C1455-14(2023)

Standard Test Method for Nondestructive Assay of Special Nuclear Material Holdup Using Gamma-Ray Spectroscopic Methods

SIGNIFICANCE AND USE
5.1 Measurement results from this test method assists in demonstrating regulatory compliance in such areas as safeguards SNM inventory control, criticality control, waste disposal, and decontamination and decommissioning (D&D). This test method can apply to the measurement of holdup in process equipment or discrete items whose gamma-ray absorption properties may be measured or estimated. This method may be adequate to accurately measure items with complex distributions of radioactive and attenuating material, however, the results are subject to larger measurement uncertainties than measurements of less complex distributions of radioactive material.  
5.2 Scan—A scan is used to provide a qualitative indication of the extent, location, and the relative quantity of holdup. It can be used to plan or supplement the quantitative measurements.  
5.3 Nuclide Mapping—Nuclide mapping measures the relative isotopic composition of the holdup at specific locations. It can also be used to detect the presence of radionuclides that emit radiation which could interfere with the assay. Nuclide mapping is best performed using a high resolution detector (such as HPGe) for best nuclide and interference detection. If the holdup is not isotopically homogeneous at the measurement location, that measured isotopic composition will not be a reliable estimate of the bulk isotopic composition.  
5.4 Quantitative Measurements—These measurements result in quantification of the mass of the measured nuclides in the holdup. They include all the corrections, such as attenuation, and descriptive information, such as isotopic composition, that are available  
5.4.1 High quality results require detailed knowledge of radiation sources and detectors, transmission of radiation, calibration, facility operations and error analysis. Judicious use of subject matter experts is required (Guide C1490).  
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...

General Information

• Status: Published
• Publication Date: 31-Dec-2022
• ICS: 27.120.30 - Fissile materials and nuclear fuel technology
• Technical Committee: C26 - Nuclear Fuel Cycle
• Drafting Committee: C26.10 - Non Destructive Assay

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: C1455 − 14 (Reapproved 2023)
Standard Test Method for
Nondestructive Assay of Special Nuclear Material Holdup
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Using Gamma-Ray Spectroscopic Methods
This standard is issued under the fixed designation C1455; 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 ization established in the Decision on Principles for the
Development of International Standards, Guides and Recom-
1.1 This test method describes gamma-ray methods used to
235 239 mendations issued by the World Trade Organization Technical
nondestructively measure the quantity of Uor Pu present
Barriers to Trade (TBT) Committee.
as holdup in nuclear facilities. Holdup may occur in any
facility where nuclear material is processed, in process
2. Referenced Documents
equipment,inexhaustventilationsystemsandinbuildingwalls
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2.1 ASTM Standards:
and floors.
C1490 GuidefortheSelection,TrainingandQualificationof
1.2 This test method includes information useful for
Nondestructive Assay (NDA) Personnel
management, planning, selection of equipment, consideration
C1592 Guide for Making Quality Nondestructive Assay
of interferences, measurement program definition, and the
Measurements
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utilization of resources (1, 2, 3, 4).
C1673 Terminology of C26.10 NondestructiveAssay Meth-
1.3 The measurement of nuclear material hold up in process
ods
equipment requires a scientific knowledge of radiation sources
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2.2 ANSI Standards:
and detectors, transmission of radiation, calibration, facility
ANSI N15.36 Measurement Control Program—
operations and uncertainty analysis. It is subject to the con-
Nondestructive Assay Measurement Control and Assur-
straints of the facility, management, budget, and schedule; plus
ance Systems
health and safety requirements. The measurement process
ANSI N15.56 Nondestructive Assay Measurements of
includes defining measurement uncertainties and is sensitive to
Nuclear Material Holdup: General Provisions
the form and distribution of the material, various backgrounds,
2.3 U.S. Nuclear Regulatory Commission Regulatory
and interferences. The work includes investigation of material
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Guides:
distributions within a facility, which could include potentially
Regulatory Guide 5.23, In SituAssay of Plutonium Residual
large holdup surface areas. Nuclear material held up in pipes,
Holdup
ductwork, gloveboxes, and heavy equipment, is usually dis-
tributedinadiffuseandirregularmanner.Itisdifficulttodefine
3. Terminology
themeasurementgeometry,toidentifytheformofthematerial,
andtomeasureitwithoutinterferencefromadjacentsourcesof 3.1 Refer to Terminology C1673 for definitions used in this
radiation. test method.
1.4 This standard does not purport to address all of the
4. Summary of Test Method
safety concerns, if any, associated with its use. It is the
responsibility of the user of this standard to establish appro- 4.1 Introduction—Holdup measurements range from the
priate safety, health, and environmental practices and deter-
solitary assay of a single item or routine measurement of a
mine the applicability of regulatory limitations prior to use. piece of equipment, to an extensive campaign of determining
1.5 This international standard was developed in accor-
the total SNM in-process inventory for a processing plant.
dance with internationally recognized principles on standard-
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This test method is under the jurisdiction ofASTM Committee C26 on Nuclear For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Fuel Cycle and is the direct responsibility of Subcommittee C26.10 on Non contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
Destructive Assay. Standards volume information, refer to the standard’s Document Summary page on
Current edition approved Jan. 1, 2023. Published January 2023. Originally the ASTM website.
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approved in 2000. Last previous edition approved in 2014 as C1455 – 14 . DOI: Available fromAmerican National Standards Institute (ANSI), 25 W. 43rd St.,
10.1520/C1455-14R23. 4th Floor, New York, NY 10036, http://www.ansi.org.
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The boldface numbers in parentheses refer to the list of references at the end of Available from the U.S. Nuclear Regulatory Commission, Washington, DC,
this standard. 20555.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
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