ASTM C1671-20
(Practice)Standard Practice for Qualification and Acceptance of Boron Based Metallic Neutron Absorbers for Nuclear Criticality Control for Dry Cask Storage Systems and Transportation Packaging
Standard Practice for Qualification and Acceptance of Boron Based Metallic Neutron Absorbers for Nuclear Criticality Control for Dry Cask Storage Systems and Transportation Packaging
SIGNIFICANCE AND USE
4.1 For criticality control of nuclear fuel in dry storage and transportation, the most commonly used neutron absorber materials are borated stainless steel alloys, borated aluminum alloys, and boron carbide aluminum alloy composites. The boron used in these neutron absorber materials may be natural or enriched in the nuclide 10B. The boron is usually incorporated either as an intermetallic phase (for example, AlB2, TiB2, CrB2, etc.) in an aluminum alloy or stainless steel, or as a stable chemical compound particulate such as boron carbide (B4C), typically in an aluminum MMC or cermet.
4.2 While other neutron absorbers continue to be investigated, 10B has been most widely used in these applications, and it is the only thermal neutron absorber addressed in this standard.
4.3 In service, many neutron absorber materials are inaccessible and not amenable to a surveillance program. These neutron absorber materials are often expected to perform over an extended period.
4.4 Qualification and acceptance procedures demonstrate that the neutron absorber material has the necessary characteristics to perform its design functions during the service lifetime.
4.5 The criticality control function of neutron absorber materials in dry cask storage systems and transportation packagings is only significant in the presence of a moderator, such as during loading of fuel under water, or water ingress resulting from hypothetical accident conditions.
4.6 The expected users of this standard include designers, neutron absorber material suppliers and purchasers, government agencies, consultants and utility owners. Typical use of the practice is to summarize practices which provide input for design specification, material qualification, and production acceptance. Adherence to this standard does not guarantee regulatory approval; a government regulatory authority may require different tests or additional tests, and may impose limits or restrictions on the use of a neutron absorbe...
SCOPE
1.1 This practice provides procedures for qualification and acceptance of neutron absorber materials used to provide criticality control by absorbing thermal neutrons in systems designed for nuclear fuel storage, transportation, or both.
1.2 This practice is limited to neutron absorber materials consisting of metal alloys, metal matrix composites (MMCs), and cermets, clad or unclad, containing the neutron absorber boron-10 (10B).
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, health, and environmental practices and determine the applicability of regulatory limitations prior to use.
1.4 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.
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Designation:C1671 −20
Standard Practice for
Qualification and Acceptance of Boron Based Metallic
Neutron Absorbers for Nuclear Criticality Control for Dry
1
Cask Storage Systems and Transportation Packaging
This standard is issued under the fixed designation C1671; 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 E8/E8M Test Methods for Tension Testing of Metallic Ma-
terials
1.1 This practice provides procedures for qualification and
E21 TestMethodsforElevatedTemperatureTensionTestsof
acceptance of neutron absorber materials used to provide
Metallic Materials
criticality control by absorbing thermal neutrons in systems
E456 Terminology Relating to Quality and Statistics
designed for nuclear fuel storage, transportation, or both.
E1225 Test Method for Thermal Conductivity of Solids
1.2 This practice is limited to neutron absorber materials
Using the Guarded-Comparative-Longitudinal Heat Flow
consisting of metal alloys, metal matrix composites (MMCs),
Technique
and cermets, clad or unclad, containing the neutron absorber
E1461 Test Method for Thermal Diffusivity by the Flash
10
boron-10 ( B).
Method
1.3 This standard does not purport to address all of the
E2971 TestMethodforDeterminationofEffectiveBoron-10
safety concerns, if any, associated with its use. It is the Areal Density in Aluminum Neutron Absorbers using
responsibility of the user of this standard to establish appro-
Neutron Attenuation Measurements
priate safety, health, and environmental practices and deter-
mine the applicability of regulatory limitations prior to use.
3. Terminology
1.4 This international standard was developed in accor-
3.1 Definitions:
dance with internationally recognized principles on standard-
3.1.1 acceptance test, n—for a neutron absorber material,
ization established in the Decision on Principles for the
quality control, tests, and inspections conducted to determine
Development of International Standards, Guides and Recom-
whether a specific production lot meets selected specified
mendations issued by the World Trade Organization Technical
material properties, characteristics, or both, so that the lot can
Barriers to Trade (TBT) Committee.
be accepted.
3.1.2 areal density, n—for neutron absorber materials with
2. Referenced Documents
flat parallel surfaces, the boron-10 per unit area of a sheet,
2
2.1 ASTM Standards:
which is equivalent to the mass per unit volume of boron-10 in
B557 Test Methods for Tension Testing Wrought and Cast
the material multiplied by the thickness of the material in
Aluminum- and Magnesium-Alloy Products
which that isotope is contained.
B557M Test Methods for Tension Testing Wrought and Cast
3.1.3 durability, n—the ability of neutron absorber materials
Aluminum- and Magnesium-Alloy Products (Metric)
to withstand service conditions without physical changes that
C791 Test Methods for Chemical, Mass Spectrometric, and
would render them unable to perform their design functions.
Spectrochemical Analysis of Nuclear-Grade Boron Car-
bide
3.1.4 lot, n—aquantityofaproductormaterialaccumulated
under conditions that are considered uniform for sampling
purposes. E456
1
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear
3.1.5 moderator, n—a material used to reduce neutron
Fuel Cycle and is the direct responsibility of Subcommittee C26.03 on Neutron
energy by scattering without appreciable capture.
Absorber Materials Specifications.
Current edition approved Jan. 1, 2020. Published January 2020. Originally
3.1.6 neutron absorber, n—anuclidethathasalargethermal
approved in 2007. Last previous edition approved in 2015 as C1671 – 15. DOI:
neutron absorption cross section (also known as a neutron
10.1520/C1671-20.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or poison).
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
3.1.7 neutron-absorber material, n—a compound, alloy,
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. composite or other material that contains a neutron absorber.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
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C1671−20
3.1.8 neutron attenuation test, n—for neutron absorber 4.3 In service, many neutron absorber materials are inac-
materials, a process in which a material is placed in a thermal cessible and not amenable to a surveillance program. These
neutron beam, and the number of neutrons transmitted through neutron absorber materials are
...
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: C1671 − 15 C1671 − 20
Standard Practice for
Qualification and Acceptance of Boron Based Metallic
Neutron Absorbers for Nuclear Criticality Control for Dry
1
Cask Storage Systems and Transportation Packaging
This standard is issued under the fixed designation C1671; 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
1.1 This practice provides procedures for qualification and acceptance of neutron absorber materials used to provide criticality
control by absorbing thermal neutrons in systems designed for nuclear fuel storage, transportation, or both.
1.2 This practice is limited to neutron absorber materials consisting of metal alloys, metal matrix composites (MMCs), and
10
cermets, clad or unclad, containing the neutron absorber boron-10 ( B).
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 safety, health, and healthenvironmental practices and determine the
applicability of regulatory limitations prior to use.
1.4 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.
2. Referenced Documents
2
2.1 ASTM Standards:
B557 Test Methods for Tension Testing Wrought and Cast Aluminum- and Magnesium-Alloy Products
B557M Test Methods for Tension Testing Wrought and Cast Aluminum- and Magnesium-Alloy Products (Metric)
C791 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Boron Carbide
E8E8/E8M Test Methods for Tension Testing of Metallic Materials [Metric] E0008_E0008M
E21 Test Methods for Elevated Temperature Tension Tests of Metallic Materials
E456 Terminology Relating to Quality and Statistics
E1225 Test Method for Thermal Conductivity of Solids Using the Guarded-Comparative-Longitudinal Heat Flow Technique
E1461 Test Method for Thermal Diffusivity by the Flash Method
E2971 Test Method for Determination of Effective Boron-10 Areal Density in Aluminum Neutron Absorbers using Neutron
Attenuation Measurements
3. Terminology
3.1 Definitions:
3.1.1 acceptance test, n—for a neutron absorber material, quality control, tests, and inspections conducted to determine whether
a specific production lot meets selected specified material properties, characteristics, or both, so that the lot can be accepted.
3.1.2 areal density, n—for neutron absorber materials with flat parallel surfaces, the density of the neutron absorber times the
boron-10 per unit area of a sheet, which is equivalent to the mass per unit volume of boron-10 in the material multiplied by the
2
thickness of the material (g/cmin ). which that isotope is contained.
3.1.3 durability, n—the ability of neutron absorber materials to withstand service conditions without physical changes that
would render them unable to perform their design functions.
1
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.03 on Neutron Absorber
Materials Specifications.
Current edition approved Jan. 1, 2015Jan. 1, 2020. Published January 2015January 2020. Originally approved in 2007. Last previous edition approved in 20072015 as
C1671C1671 – 15.-07. DOI: 10.1520/C1671-15. 10.1520/C1671-20.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1
---------------------- Page: 1 ----------------------
C1671 − 20
3.1.4 lot, n—a quantity of a product or material accumulated under conditions that are considered uniform for sampling
purposes. E456
3.1.5 moderator, n—a material used to reduce neutron energy by scattering without appreciable capture.
3.1.6 neutron absorber, n—a nuclide that has a large thermal neutron absorption cross section (also known as a neutron poi
...
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