Standard Test Method for Nondestructive Assay of Nuclear Material in Scrap and Waste by Passive-Active Neutron Counting Using <sup>252</sup>Cf Shuffler

SIGNIFICANCE AND USE
This test method is used to determine the U and Pu content of scrap and waste in containers. Active measurement times have typically been 100 to 1000 s. Passive measurement times have typically been 400 s to several hours. The following limits may be further restricted depending upon specific matrix, calibration material, criticality safety, or counting equipment considerations.
The passive measurement has been applied to benign matrices in 208 L drums with Pu content ranging from 30 mg to 1 kg.
The active measurement has been applied to waste drums with 235U content ranging from about 100 mg to 1 kg.
This test method can be used to demonstrate compliance with the radioactivity levels specified in safeguards, waste, disposal, and environmental regulations (for example, see NRC regulatory guides 5.11, 5.53, DOE Order 5820.2a, and 10CFR61 sections 61.55 and sections 61.56, 40CFR191, and DOE/WIPP-069).  
This test method could be used to detect diversion attempts that use shielding to encapsulate nuclear material.
The bias of the measurement results is related to the item size and density, the homogeneity and composition of the matrix, and the quantity and distribution of the nuclear material. The precision of the measurement results is related to the quantity of nuclear material and the count time of the measurement.
For both the matrix-specific and the matrix-correction approaches, the method assumes the calibration materials match the items to be measured with respect to the homogeneity and composition of the matrix, the neutron moderator and absorber content, and the quantity of nuclear material, to the extent they affect the measurement.
It is recommended that measurements be made on small containers of scrap and waste before they are combined in large containers. Special arrangement may be required to assay small containers to best effect in a large cavity general purpose shuffer.
It is recommended that measurements be made on containers with homog...
SCOPE
1.1 This test method covers the nondestructive assay of scrap and waste items for U, Pu, or both, using a 252Cf shuffler. Shuffler measurements have been applied to a variety of matrix materials in containers of up to several 100 L. Corrections are made for the effects of matrix material. Applications of this test method include measurements for safeguards, accountability, TRU, and U waste segregation, disposal, and process control purposes (1, 2, 3).  
1.1.1 This test method uses passive neutron coincidence counting (4) to measure the 240Pu-effective mass. It has been used to assay items with total Pu contents between 0.03 g and 1000 g. It could be used to measure other spontaneously fissioning isotopes such as Cm and Cf. It specifically describes the approach used with shift register electronics; however, it can be adapted to other electronics.  
1.1.2 This test method uses neutron irradiation with a moveable Cf source and counting of the delayed neutrons from the induced fissions to measure the 235U equivalent fissile mass. It has been used to assay items with 235U contents between 0.1 g and 1000 g. It could be used to assay other fissile and fissionable isotopes.
1.2 This test method requires knowledge of the relative isotopic composition (See Test Method C 1030) of the special nuclear material to determine the mass of the different elements from the measurable quantities.
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.4 The techniques described in this test method have been applied to materials other than scrap and waste. These other applications are not addressed in this test method.
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 and health practices and determine the applicability...

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ASTM C1316-08 - Standard Test Method for Nondestructive Assay of Nuclear Material in Scrap and Waste by Passive-Active Neutron Counting Using <sup>252</sup>Cf Shuffler
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Standards Content (Sample)

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: C1316 − 08
Standard Test Method for
Nondestructive Assay of Nuclear Material in Scrap and
252
Waste by Passive-Active Neutron Counting Using Cf
1
Shuffler
This standard is issued under the fixed designation C1316; 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 1.5 This standard does not purport to address all of the
safety concerns, if any, associated with its use. It is the
1.1 This test method covers the nondestructive assay of
252 responsibility of the user of this standard to establish appro-
scrapandwasteitemsforU,Pu,orboth,usinga Cfshuffler.
priate safety and health practices and determine the applica-
Shufflermeasurementshavebeenappliedtoavarietyofmatrix
bility of regulatory limitations prior to use. Specific precau-
materials in containers of up to several 100 L. Corrections are
tionary statements are given in Section 8.
madefortheeffectsofmatrixmaterial.Applicationsofthistest
method include measurements for safeguards, accountability,
2. Referenced Documents
TRU, and U waste segregation, disposal, and process control
3
2
2.1 ASTM Standards:
purposes (1, 2, 3).
C1009Guide for Establishing and Maintaining a Quality
1.1.1 This test method uses passive neutron coincidence
240
AssuranceProgramforAnalyticalLaboratoriesWithinthe
counting (4) to measure the Pu-effective mass. It has been
Nuclear Industry
used to assay items with total Pu contents between 0.03 g and
C1030TestMethodforDeterminationofPlutoniumIsotopic
1000 g. It could be used to measure other spontaneously
Composition by Gamma-Ray Spectrometry
fissioningisotopessuchasCmandCf.Itspecificallydescribes
C1068Guide for Qualification of Measurement Methods by
the approach used with shift register electronics; however, it
a Laboratory Within the Nuclear Industry
can be adapted to other electronics.
C1128Guide for Preparation of Working Reference Materi-
1.1.2 This test method uses neutron irradiation with a
als for Use in Analysis of Nuclear Fuel Cycle Materials
moveableCfsourceandcountingofthedelayedneutronsfrom
235
C1133Test Method for Nondestructive Assay of Special
the induced fissions to measure the U equivalent fissile
235
Nuclear Material in Low-Density Scrap and Waste by
mass. It has been used to assay items with U contents
Segmented Passive Gamma-Ray Scanning
between0.1gand1000g.Itcouldbeusedtoassayotherfissile
C1156Guide for Establishing Calibration for a Measure-
and fissionable isotopes.
ment Method Used toAnalyze Nuclear Fuel Cycle Mate-
1.2 This test method requires knowledge of the relative
rials
isotopic composition (See Test Method C1030) of the special
C1207Test Method for NondestructiveAssay of Plutonium
nuclearmaterialtodeterminethemassofthedifferentelements
in Scrap and Waste by Passive Neutron Coincidence
from the measurable quantities.
Counting
1.3 The values stated in SI units are to be regarded as
C1210Guide for Establishing a Measurement System Qual-
standard. No other units of measurement are included in this
ity Control Program for Analytical Chemistry Laborato-
standard.
ries Within the Nuclear Industry
C1215Guide for Preparing and Interpreting Precision and
1.4 The techniques described in this test method have been
Bias Statements in Test Method Standards Used in the
applied to materials other than scrap and waste. These other
Nuclear Industry
applications are not addressed in this test method.
C1490GuidefortheSelection,TrainingandQualificationof
Nondestructive Assay (NDA) Personnel
1
ThistestmethodisunderthejurisdictionofASTMCommitteeC26onNuclear
C1592Guide for Nondestructive Assay Measurements
Fuel Cycle and is the direct responsibility of Subcommittee C26.10 on Non
Destructive Assay.
CurrenteditionapprovedJune1,2008.PublishedJuly2008.Originallyapproved
3
in 1995. Last previous edition approved in 2001 as C1316–01. DOI: 10.1520/ For referenced ASTM standards, visit the ASTM website, www.astm.org, or
C1316-08. contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
2
The boldface numbers in parentheses refer to a list of references at the end of Standards volume information, refer to the standard’s Document Summary page on
this test method. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
C1316 − 08
C1673Terminology of C26.10 NondestructiveAssay Meth- 4.2 Either corrections are made for the effects of neutron
ods absorbers and moderators in the matrix, or a matrix-specific
calibration is used. The effect that needs correction is the
2.2 ANS
...

This document is not anASTM standard and is intended only to provide the user of anASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately,ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation:C1316–01 Designation:C1316–08
Standard Test Method for
Nondestructive Assay of Nuclear Material in Scrap and
Waste by Passive-Active Neutron Counting Using
252
1
aUsing Cf Shuffler
This standard is issued under the fixed designation C1316; 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
1.1 ThistestmethodcoversthenondestructiveassayofscrapandwasteitemsforuraniumandplutoniumcontentU,Pu,orboth,
252
usinga Cfshuffler.Shufflermeasurementsproviderapidresultsandcanbeappliedtoavarietyofmatrixmaterialsincontainers
as large as 208-litre drums. Corrections are made for the effects of matrix material.This test method has been used to assay items
containing uranium, plutonium, or both. Applications of this test method include measurements for safeguards, accountability,
TRU, and U waste segregation, disposal, and process control purposes Cf shuffler. Shuffler measurements have been applied
toavarietyofmatrixmaterialsincontainersofuptoseveral100L.Correctionsaremadefortheeffectsofmatrixmaterial.
Applications of this test method include measurements for safeguards, accountability, TRU, and U waste segregation,
2
disposal, and process control purposes (1, 2, 3).
240 242
1.1.1 Thistestmethodusespassiveneutroncoincidencecounting(4)tomeasure238Pu, the Pu, and Pu. Pu-effective mass. It has been
used to assay items with plutonium total Pu contents between 0.03 g and 1000 g. It could be used to measure other spontaneously fissioning isotopes such as Cm and Cf.
It specifically describes the approach used with shift register electronics; however, it can be adapted to other electronics.
1.1.2 ThistestmethodusesneutronirradiationwithamoveablecaliforniumCfsourceandcountingofthedelayedneutronsfrom
235
235 U equivalent fissile mass. It has been used to assay items with
the induced fissions to measure the U. It has been used to assay items with U
contents between 0.1 g and 1000 g. It could be used to assay other fissionable isotopes.
1.2This test method requires knowledge of the relative isotopic composition to determine the mass of the different elements.
1.3Thistestmethodmaygivebiasedresultsformeasurementsofcontainersthatincludelargequantitiesofhydrogen.Ucontents
between 0.1 g and 1000 g. It could be used to assay other fissile and fissionable isotopes.
1.2 This test method requires knowledge of the relative isotopic composition (See Test Method C1030) of the special nuclear
material to determine the mass of the different elements from the measurable quantities.
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
1.4 The techniques described in this test method have been applied to materials other than scrap and waste. These other
applications are not addressed in this test method.
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 and health practices and determine the applicability of regulatory
limitations prior to use. Specific precautionary statements are given in Section 8.
2. Referenced Documents
3
2.1 ASTM Standards: C859Terminology Relating to Nuclear Materials C986Guide for Developing Training Programs in the
3
Nuclear Fuel Cycle
C1009 GuideforEstablishingaQualityAssuranceProgramforAnalyticalChemistryLaboratoriesWithintheNuclearIndustry
C1030 Test Method for Determination of Plutonium Isotopic Composition by Gamma-Ray Spectrometry
C1068 Guide for Qualification of Measurement Methods by a Laboratory Within the Nuclear Industry
C1128 Guide for Preparation of Working Reference Materials for Use in the Analysis of Nuclear Fuel Cycle Materials
C1133 Test Method for Nondestructive Assay of Special Nuclear Material in Low-Density Scrap and Waste by Segmented
Passive Gamma-Ray Scanning
1
ThistestmethodisunderthejurisdictionofASTMCommitteeC26onNuclearFuelCycleandisthedirectresponsibilityofSubcommitteeC26.10onNondDestructive
Assay.
Current edition approved June 10, 2001.1, 2008. Published September 2001.July 2008. Originally published as C1316–95.approved in 1995. Last previous edition
C1316–95.approved in 2001 as C1316–01.
2
The boldface numbers in parentheses refer to a list of references at the end of this test method.
3
Forrefere
...

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