ASTM E2971-16

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.

General Information

• Status: Historical
• Publication Date: 31-May-2016
• ICS: 19.100 - Non-destructive testing
• Technical Committee: E07 - Nondestructive Testing
• Drafting Committee: E07.05 - Radiology (Neutron) Method

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: E2971 − 16
Standard Test Method for
Determination of Effective Boron-10 Areal Density in
Aluminum Neutron Absorbers using Neutron Attenuation
1
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
2
1.1 This test method is intended for quantitative determina-
2.1 ASTM Standards
10
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
pared to attenuation values for calibration standards allowing
E1316Terminology for Nondestructive Examinations
10
determination of the effective B areal density. This test is
typically performed in a laboratory setting. This method is
3. Terminology
valid only under the following conditions:
3.1 Fordefinitionsoftermsusedinthistestmethod,referto
10
1.1.1 The absorber contains B in an aluminum or alumi-
Terminology E1316.
num alloy matrix.
10
1.1.2 The primary neutron absorber is B.
4. Summary of Test Method
1.1.3 The test specimen has uniform thickness.
4.1 In this test method, aluminum neutron absorbers are
1.1.4 The test specimen has a testing surface area at least
placed in a thermal neutron beam and the number of neutrons
twice that of the thermal neutron beam’s surface cross-
transmitted through the material in a known period of time is
10
sectional area.
counted. The neutron count can be converted to B areal
1.1.5 The calibration standards of uniform composition density by performing the same test on a series of appropriate
span the range of areal densities being measured.
calibration standards and comparing the results.
1.1.6 Thearealdensityisbetween0.001and0.080gramsof
4.2 This test method uses a beam of neutrons with the
10 2
B per cm .
neutron energy spectrum thermalized by an appropriate mod-
1.1.7 The thermalized neutron beam is derived from a
erator. Other methods such as neutron diffraction may be used
fission reactor, sub-critical assembly, accelerator or neutron
to generate a thermal neutron beam.
generator.
4.3 A beam of thermal neutrons shall be derived from a
fission reactor, sub-critical assembly, accelerator or neutron
1.2 The values stated in SI units are to be regarded as
standard. No other units of measurement are included in this generator.
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
10
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.
1
This test method is under the jurisdiction of ASTM Committee E07 on
Nondestructive Testing and is the direct responsibility of Subcommittee E07.05 on
2
Radiology (Neutron) Method. For referenced ASTM standards, visit the ASTM website, www.astm.org, or
Current edition approved June 1, 2016. Published June 2016. Originally contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
approved in 2014. Last previous edition approved in 2014 as E2971-14. DOI: Standards volume information, refer to the standard’s Document Summary page on
10.1520/E2971-16. the ASTM website.
*A Summary of Changes section appears at the end of this standard
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E2971 − 16
5.2 Areal density measurements are also used in the inves- 8. Hazards
10
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 Stand
...

This document is not an ASTM standard and is intended only to provide the user of an ASTM 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: E2971 − 14 E2971 − 16
Standard Test Method for
Determination of Effective Boron-10 Areal Density in
Aluminum Neutron Absorbers using Neutron Attenuation
1
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. 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 Scope*
10 10
1.1 This test method is intended for quantitative determination of effective boron-10 ( B) areal density (mass per area of B,
10 2
usually measured in grams- B/cm ) 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
10
effective B areal density. This test is typically performed in a laboratory setting. This method is valid only under the following
conditions:
10
1.1.1 The absorber contains B in an aluminum or aluminum alloy matrix.
10
1.1.2 The primary neutron absorber is B.
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.
10 2
1.1.6 The areal density is between 0.001 and 0.080 grams of B per cm .
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.
2. Referenced Documents
2
2.1 ASTM Standards
C1671 Practice for Qualification and Acceptance of Boron Based Metallic Neutron Absorbers for Nuclear Criticality Control for
Dry Cask Storage Systems and Transportation Packaging
E1316 Terminology for Nondestructive Examinations
3. Terminology
3.1 For definitions of terms used in this test method, refer to Terminology E1316.
4. Summary of Test Method
4.1 In this test method, aluminum neutron absorbers are placed in a thermal neutron beam and the number of neutrons
10
transmitted through the material in a known period of time is counted. The neutron count can be converted to B areal density
by performing the same test on a series of appropriate calibration standards and comparing the results.
4.2 This test method uses a beam of neutrons with the neutron energy spectrum thermalized by an appropriate moderator. Other
methods such as neutron diffraction may be used to generate a thermal neutron beam.
4.3 A beam of thermal neutrons shall be derived from a fission reactor, sub-critical assembly, accelerator or neutron generator.
1
This test method is under the jurisdiction of ASTM Committee E07 on Nondestructive Testing and is the direct responsibility of Subcommittee E07.05 on Radiology
(Neutron) Method.
Current edition approved June 1, 2014June 1, 2016. Published July 2014June 2016. Originally approved in 2014. Last previous edition approved in 2014 as E2971-14.
DOI: 10.1520/E2971-14.10.1520/E2971-16.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
*A Summary of Changes section appears at the end of this standard
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
E2971 − 16
5. Significance and Use
10
5.1 The typical use of this test method is determination of B 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.
10
5.2 Areal density measurements are also used in the investigation of the uniformity in B spatial distribution.
5.3 The expected users of this s
...