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
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.
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.
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.
Qualification and acceptance procedures demonstrate that the neutron absorber material has the necessary characteristics to perform its design functions during the service lifetime.
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.
The expected users of this standard include designers, neutron absorber material suppliers and purchasers, government agencies, consultants and utility owners. 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 absorber material.
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 and health practices and determine the applicability of regulatory limitations prior to use.

General Information

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Historical
Publication Date
14-Jul-2007
Current Stage
Ref Project

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ASTM C1671-07 - Standard Practice for Qualification and Acceptance of Boron Based Metallic Neutron Absorbers for Nuclear Criticality Control for Dry Cask Storage Systems and Transportation Packaging
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Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
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Designation:C1671 −07
StandardPractice 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 E1461 Test Method for Thermal Diffusivity by the Flash
Method
1.1 This practice provides procedures for qualification and
acceptance of neutron absorber materials used to provide
3. Terminology
criticality control by absorbing thermal neutrons in systems
designed for nuclear fuel storage, transportation, or both. 3.1 Definitions:
3.1.1 acceptance test, n—for a neutron absorber material,
1.2 This practice is limited to neutron absorber materials
quality control, tests, and inspections conducted to determine
consisting of metal alloys, metal matrix composites (MMCs),
whether a specific production lot meets selected specified
and cermets, clad or unclad, containing the neutron absorber
10
material properties, characteristics, or both, so that the lot can
boron-10 ( B).
be accepted.
1.3 This standard does not purport to address all of the
3.1.2 areal density, n—for neutron absorber materials with
safety concerns, if any, associated with its use. It is the
flat parallel surfaces, the density of the neutron absorber times
responsibility of the user of this standard to establish appro-
2
the thickness of the material (g/cm ).
priate safety and health practices and determine the applica-
bility of regulatory limitations prior to use.
3.1.3 durability, n—the ability of neutron absorber materials
to withstand service conditions without physical changes that
2. Referenced Documents
would render them unable to perform their design functions.
2
2.1 ASTM Standards:
3.1.4 lot, n—aquantityofaproductormaterialaccumulated
B557 Test Methods for Tension Testing Wrought and Cast
under conditions that are considered uniform for sampling
Aluminum- and Magnesium-Alloy Products
purposes. E456
B557M Test Methods for Tension Testing Wrought and Cast
3.1.5 moderator, n—a material used to reduce neutron
Aluminum- and Magnesium-Alloy Products (Metric)
energy by scattering without appreciable capture.
C791 Test Methods for Chemical, Mass Spectrometric, and
3.1.6 neutron absorber, n—anuclidethathasalargethermal
Spectrochemical Analysis of Nuclear-Grade Boron Car-
neutron absorption cross section (also known as a neutron
bide
poison).
E8 Test Methods for Tension Testing of Metallic Materials
E21 TestMethodsforElevatedTemperatureTensionTestsof
3.1.7 neutron-absorber material, n—a compound, alloy,
Metallic Materials
composite or other material that contains a neutron absorber.
E456 Terminology Relating to Quality and Statistics
3.1.8 neutron attenuation test, n—for neutron absorber
E1225 Test Method for Thermal Conductivity of Solids by
materials, a process in which a material is placed in a thermal
Means of the Guarded-Comparative-Longitudinal Heat
neutron beam, and the number of neutrons transmitted through
Flow Technique
the material in a specified period of time is counted. The
neutron count can be converted to areal density by performing
the same test on a series of appropriate calibration standards
1
This practice is under the jurisdiction of ASTM Committee C26 on Nuclear
and comparing the results.
Fuel Cycle and is the direct responsibility of Subcommittee C26.03 on Neutron
Absorber Materials Specifications.
3.1.9 neutron cross section, [barn], n—a measure of the
Current edition approved July 15, 2007. Published August 2007. DOI: 10.1520/
probability that a neutron will interact with a nucleus in the
C1671-07.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or absorbing medium and is a function of the neutron energy.
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
3.1.10 open porosity, n—the volume fraction of all pores,
Standards volume information, refer to the standard’s Document Summary page on
the ASTM website. voids, and channels within a solid mass that are interconnected
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

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C1671−07
with each other and communicate with the external surface, such as during loading of fuel under water, or water ingress
and thus are measurable by gas or liquid penetration. C242, resulting from hypothetical accident conditions.
C21
4.6 The expected users of this standard include designers,
3.1.11 packaging, n—in
...

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