Standard Test Method for Determination of Effective Boron-10 Areal Density in Aluminum Neutron Absorbers using Neutron Attenuation Measurements

SIGNIFICANCE AND USE
5.1 The typical use of this test method is determination of 10B areal density in aluminum neutron absorber materials used to control criticality in systems such as: spent nuclear fuel dry storage canisters, transfer/transport nuclear fuel containers, spent nuclear fuel pools, and fresh nuclear fuel transport containers.  
5.2 Areal density measurements are also used in the investigation of the uniformity in 10B spatial distribution.  
5.3 The expected users of this standard include designers, suppliers, neutron absorber users, testing labs, and consultants in the field of nuclear criticality analysis.  
5.4 Another known method used to determine areal density of 10B in aluminum neutron absorbers is an analytical chemical method as mentioned in Practice C1671. However, the analytical chemical method does not measure the “effective” 10B areal density as measured by neutron attenuation.
SCOPE
1.1 This test method is intended for quantitative determination of effective boron-10 (10B) areal density (mass per area of 10B, usually measured in grams-10B/cm2 ) in aluminum neutron absorbers. The attenuation of a thermal neutron beam transmitted through an aluminum neutron absorber is compared to attenuation values for calibration standards allowing determination of the effective 10B areal density. This test is typically performed in a laboratory setting. This method is valid only under the following conditions:  
1.1.1 The absorber contains 10B in an aluminum or aluminum alloy matrix.  
1.1.2 The primary neutron absorber is 10B.  
1.1.3 The test specimen has uniform thickness.  
1.1.4 The test specimen has a testing surface area at least twice that of the thermal neutron beam’s surface cross-sectional area.  
1.1.5 The calibration standards of uniform composition span the range of areal densities being measured.  
1.1.6 The areal density is between 0.001 and 0.080 grams of 10B per cm2.  
1.1.7 The thermalized neutron beam is derived from a fission reactor, sub-critical assembly, accelerator or neutron generator.  
1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.3 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.

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31-May-2014
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ASTM E2971-14 - Standard Test Method for Determination of Effective Boron-10 Areal Density in Aluminum Neutron Absorbers using Neutron Attenuation Measurements
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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: E2971 − 14
StandardTest Method for
Determination of Effective Boron-10 Areal Density in
Aluminum Neutron Absorbers using Neutron Attenuation
Measurements
This standard is issued under the fixed designation E2971; 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 2. Referenced Documents
1.1 This test method is intended for quantitative determina- 2.1 ASTM Standards
tion of effective boron-10 ( B) areal density (mass per area of
C1671Practice for Qualification and Acceptance of Boron
10 10 2
B, usually measured in grams- B/cm ) in aluminum neu- Based Metallic NeutronAbsorbers for Nuclear Criticality
tron absorbers. The attenuation of a thermal neutron beam Control for Dry Cask Storage Systems andTransportation
transmitted through an aluminum neutron absorber is com- Packaging
E1316Terminology for Nondestructive Examinations
pared to attenuation values for calibration standards allowing
determination of the effective B areal density. This test is
3. Terminology
typically performed in a laboratory setting. This method is
valid only under the following conditions:
3.1 Fordefinitionsoftermsusedinthistestmethod,referto
1.1.1 The absorber contains B in an aluminum or alumi-
Terminology E1316.
num alloy matrix.
4. Summary of Test Method
1.1.2 The primary neutron absorber is B.
4.1 In this test method, aluminum neutron absorbers are
1.1.3 The test specimen has uniform thickness.
placed in a thermal neutron beam and the number of neutrons
1.1.4 The test specimen has a testing surface area at least
transmitted through the material in a known period of time is
twice that of the thermal neutron beam’s surface cross-
counted. The neutron count can be converted to B areal
sectional area.
density by performing the same test on a series of appropriate
1.1.5 The calibration standards of uniform composition
calibration standards and comparing the results.
span the range of areal densities being measured.
4.2 This test method uses a beam of neutrons with the
1.1.6 Thearealdensityisbetween0.001and0.080gramsof
10 2 neutron energy spectrum thermalized by an appropriate mod-
B per cm .
erator. Other methods such as neutron diffraction may be used
1.1.7 The thermalized neutron beam is derived from a
to generate a thermal neutron beam.
fission reactor, sub-critical assembly, accelerator or neutron
4.3 A beam of thermal neutrons shall be derived from a
generator.
fission reactor, sub-critical assembly, accelerator or neutron
1.2 The values stated in SI units are to be regarded as
generator.
standard. No other units of measurement are included in this
standard.
5. Significance and Use
1.3 This standard does not purport to address all of the
5.1 The typical use of this test method is determination of
safety concerns, if any, associated with its use. It is the
B areal density in aluminum neutron absorber materials used
responsibility of the user of this standard to establish appro-
to control criticality in systems such as: spent nuclear fuel dry
priate safety and health practices and determine the applica-
storage canisters, transfer/transport nuclear fuel containers,
bility of regulatory limitations prior to use.
spent nuclear fuel pools, and fresh nuclear fuel transport
containers.
This test method is under the jurisdiction of ASTM Committee E07 on
Nondestructive Testing and is the direct responsibility of Subcommittee E07.05 on For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Radiology (Neutron) Method. contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
CurrenteditionapprovedJune1,2014.PublishedJuly2014.Originallyapproved Standards volume information, refer to the standard’s Document Summary page on
in 2014. DOI: 10.1520/E2971-14. the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
E2971 − 14
5.2 Areal density measurements are also used in the inves- 8. Hazards
tigation of the uniformity in B spatial distribution.
8.1 This test method does not address radiation safety. It is
the responsibility of the user of this test method to establish
5.3 The expected users of this standard include designers,
suppliers, neutron absorber users, testing labs, and consultants appropriate safety procedures, if necessary.
in the field of nuclear criticality analysis.
9. Calibration and Standardization
5.4 Another known method used to determine areal density
9.1 A series of standards with uniform, homogenous, and
of Binaluminumneutronabsorbersisananalyticalchemical
accurately known B areal densities is necessary for quanti-
method as mentioned in Practice C1671. However, the analyti-
tative interpretation of the counting data acquired in the
calchemicalmethoddoesnotmeasurethe“effective” Bareal
density as measured by neutron attenuation. attenuation measurements. If the standards are not chemically
homogenous, the user of this standard must demonstrate that
the uniformity of the sample’s B is sufficient to meet the
6. Interferences
intention of this standard. These standards shall include B
6.1 Counts not associated with attenuation by the sample
arealdensitiesspanningtherangeofarealdensitiesexpectedin
shall be accounted for by measuring and incorporating back-
the test specimens. Calibration standards must have a testing
ground readings. Background reading will vary depending on
surface area at least twice that of the thermal neutron beam’s
the set up of the electronics of the system and the presence/
cross-sectional area
absence of high energy photons.
9.2 The number of standards used shall take into consider-
6.2 Measuredcountratesapproachingthebackgroundcount
ation the magnitude and range of the sample’s target areal
rate may limit the abilities of a system to accurately measure
densityandrequiredaccuracyofthemeasurement.Aminimum
highly attenuating samples.
of three standards shall be used. The facility, calibration
standards, and the test samples’ areal densities should be
6.3 Coincidence loss may occur in the B detector(s) when
considered when determining the spacing of the calibration
the neutron count rate is too high.
areal densities. For example, when using a poly-energetic
beam, the optimal spacing of the calibration standard’s areal
7. Apparatus
densities will not be uniform.
7.1 The essential features required for areal density mea-
9.3 Aluminum shim plate(s) may be required with the
surement are the following:
standards to simulate the aluminum in the test specimen.
7.1.1 Source of thermal neutrons of an appropriate intensity
Because the absorption and scattering cross-sections of alumi-
to obtain the desired counting statistics in a reasonable time
num are very small, exact replication of the aluminum in the
period while not saturating the detector. If the counting rate is
testspecimensisnotcritical.Scatteringplaysaveryminorrole
too high, pulses can pile up, causing counts to be lost in what
in neutron attenuation measurements. The standards shall be
iscalled“coincidenceloss.”Thedetectortimeconstantinmost
shimmed to ensure an equivalent or larger scattering contribu-
modern counting circuits is sufficiently small to accommodate
6 tion than the test specimen.
upto2×10 CPM.However,checksshouldbemadetoassure
that the coincidence loss is not excessive.
9.4 If the material used for calibration standards contains
neutron absorbing or scattering nuclides not present in the test
7.1.2 A neutron beam intensity monitor for correction of
specimens, or vice versa, the effect of these nuclides on the
neutron intensity fluctuations.
accuracy of the measurements shall be addressed.
7.1.3 A collimator long enough to result in a thermal
neutronbeamwithaminimalbeamdivergencethatwillreduce
10. Procedure
scattering contributions and B measurement variability with
samplethickness.Thecollimatormaybeevacuated,filledwith
10.1 The following procedure describes the method used to
air, or an inert gas.
measure the calibration standards as well as the samples.
7.1.4 A physical support, preferably adjustable, to mount
Calibration,background,andbeamintensityshallbemeasured
the standard and the test specimens in the neutron beam.
each time a set of samples are undergoing investigation, so the
7.1.5 A neutron detector, usually a boron tri-fluoride (BF ) measurement
...

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