Standard Test Method for Nondestructive Assay of Special Nuclear Material in Low Density Scrap and Waste by Segmented Passive Gamma-Ray Scanning

SCOPE
1.1 This test method covers the nondestructive assay of gamma-ray emitting special nuclear materials (SNMs) in low-density scrap or waste, packaged in cylindrical containers (with measured transmission values greater than 1%). High resolution gamma-ray spectroscopy is used to detect and measure the nuclides of interest and to measure and correct for average gamma-ray attenuation in discrete vertical segments of the container. Corrections are also made for counting losses occasioned by signal processing characteristics (1-3).  
1.2 Two conditions must be met to optimize assay results as follows:
1.2.1 The particles containing the nuclides of interest must be small to minimize self absorption of emitted gamma radiation.
1.2.2 The mixture of material within a package segment must be reasonably uniform in order to apply an attenuation correction factor, computed from a single measurement of item transmission through the segment.
1.3 The assay technique may be applicable to loadings of from one to several hundred grams of nuclide with more restricted ranges to be applicable, depending on specific packaging and counting equipment considerations. Measured transmission values must be greater than 1% to permit valid attenuation corrections.
1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.  
1.5 This standard may involve hazardous materials, operations, and equipment. 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. Specific precautionary statements are given in Section 9.

General Information

Status
Historical
Publication Date
31-Dec-1995
Technical Committee
Current Stage
Ref Project

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ASTM C1133-96 - Standard Test Method for Nondestructive Assay of Special Nuclear Material in Low Density Scrap and Waste by Segmented Passive Gamma-Ray Scanning
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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.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: C 1133 – 96
AMERICAN SOCIETY FOR TESTING AND MATERIALS
100 Barr Harbor Dr., West Conshohocken, PA 19428
Reprinted from the Annual Book of ASTM Standards. Copyright ASTM
Standard Test Method for
Nondestructive Assay of Special Nuclear Material in Low-
Density Scrap and Waste by Segmented Passive Gamma-
1
Ray Scanning
This standard is issued under the fixed designation C 1133; 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 (e) indicates an editorial change since the last revision or reapproval.
1. Scope restricted ranges to be applicable depending on specific pack-
aging and counting equipment considerations. Measured trans-
1.1 This test method covers the nondestructive assay of
mission values must be available to permit valid attenuation
gamma-ray emitting special nuclear materials (SNMs), most
235 239 241
corrections.
commonly U, Pu, and Am, in low-density scrap or
1.5 The values stated in SI units are to be regarded as the
waste, packaged in cylindrical containers. High-resolution
standard. The values given in parentheses are for information
gamma-ray spectroscopy is used to detect and measure the
only.
nuclides of interest and to measure and correct for gamma-ray
1.6 This standard does not purport to address all of the
attenuation in vertical segments of the container. Corrections
safety concerns, if any, associated with its use. It is the
are also made for counting losses occasioned by signal
2 responsibility of the user of this standard to establish appro-
processing limitations (1–3).
priate safety and health practices and determine the applica-
1.2 There are currently at least three systems in use or under
bility of regulatory limitations prior to use. Specific precau-
active development for determining the attenuation experi-
tionary statements are given in Section 8.
enced by the radiation emitted from the nuclide of interest.
These methods include the following: the original segmented
2. Referenced Documents
gamma scan transmission procedure (SGS) (4,5); a procedure
2.1 ASTM Standards:
involving measurements of the transmission at multiple ener-
C 982 Guide for Selecting Components for Energy-
gies combined with corrections for nuclide lumps based on
3
Dispersive X-Ray Fluorescence (XRF) Systems
assays of the nuclide of interest at multiple energies (MESGS)
C 1128 Guide for Preparation of Working Reference Mate-
(6–8); and tomographic scanning procedures (TGSS) (9,10).
rials for Use in the Analysis of Nuclear Fuel Cycle
1.2.1 The simplest procedure, the original segmented
3
Materials
gamma scan transmission procedure, will be covered in detail
C 1156 Guide for Establishing Calibration for a Measure-
in the remainder of the main body of this test method and
ment Method Used to Analyze Nuclear Fuel Cycle Mate-
Annex A1.
3
rials
1.2.2 Due to the limited experience and literature document-
C 1207 Test Method for Nondestructive Assay of Plutonium
ing the MESGS and TGS procedures, discussion in this test
in Scrap and Waste by Passive Neutron Coincidence
method will be limited to the above references.
3
Counting
1.3 Two conditions must be met to optimize SGS assay
C 1210 Guide for Establishing a Measurement System
results as follows:
Quality Control Program for Analytical Chemistry Labo-
1.3.1 The particles containing the nuclides of interest must
3
ratories within the Nuclear Industry
be small to minimize self absorption of emitted gamma
E 181 Test Methods for Detector Calibration and Analysis
radiation.
4
of Radionuclides
1.3.2 The mixture of material within each item segment
5
2.2 ANSI Standards:
must be sufficiently uniform to apply an attenuation correction
ANSI N15.20 Guide to Calibrating Nondestructive Assay
factor, computed from a measurement of gamma-ray transmis-
Systems
sion through the segment.
ANSI N15.35 Guide to Preparing Calibration Material for
1.4 The assay technique may be applicable to loadings of
Nondestructive Assay Systems that Count Passive Gamma
from one to several hundred grams of nuclide, with more
Rays
1
This test method is under the jurisdiction of ASTM Committee C-26 on Nuclear
Fuel Cycle and is the direct responsibility of Subcommittee C26.10 on Nondestruc-
3
tive Assay. Annual Book of ASTM Standards, Vol 12.01.
4
Current edition approved July 10, 1996. Published September 1996. Annual Book of ASTM Standards, Vol 12.02.
2 5
The boldface numbers in parentheses refer to the list of references at the end of Available from American National Standards Institute, 11 W. 42nd St., 13th
this test method. Floor, New York, NY 10036.
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