ASTM C784-05
(Specification)Standard Specification for Nuclear-Grade Aluminum Oxide-Boron Carbide Composite Pellets
Standard Specification for Nuclear-Grade Aluminum Oxide-Boron Carbide Composite Pellets
ABSTRACT
This specification applies to composite pellets composed of mixtures of nuclear-grade aluminum oxide and boron carbide that may be ultimately used in a reactor core, for example, in neutron absorber rods. Specimens shall be sampled and tested as appropriate, and shall adhere accordingly to required chemical compositions, physical dimensions, density, boron carbide homogeneity, mechanical properties, visual appearance, end and circumferential chips, cracks, and fissures and other defects.
SCOPE
1.1 This specification applies to pellets composed of mixtures of aluminum oxide and boron carbide that may be ultimately used in a reactor core, for example, in neutron absorber rods.
1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
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Standards Content (Sample)
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Designation: C784 – 05
Standard Specification for
Nuclear-Grade Aluminum Oxide-Boron Carbide Composite
1
Pellets
This standard is issued under the fixed designation C784; 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 (10CFR50), Domestic Licensing of Production and Utili-
4
zation Facilities
1.1 This specification applies to pellets composed of mix-
tures of aluminum oxide and boron carbide that may be
3. Terminology
ultimately used in a reactor core, for example, in neutron
3.1 Definitions:
absorber rods.
3.1.1 Terms shall be defined in accordance with Terminol-
1.2 The values stated in SI units are to be regarded as the
ogy C859 except for the following:
standard. The values given in parentheses are for information
3.2 Definitions of Terms Specific to This Standard:
only.
3.2.1 buyer—organization issuing the purchase order.
2. Referenced Documents 3.2.2 pellet—a fabricated geometric shape of aluminum
2 oxide-boron carbide having a chemical composition as de-
2.1 ASTM Standards:
scribed in Section 4.
C559 Test Method for Bulk Density by Physical Measure-
3.2.3 pellet lot—that quantity of pellets produced from one
ments of Manufactured Carbon and Graphite Articles
powder mixture lot using one set of mixing and process
C750 Specification for Nuclear-Grade Boron Carbide Pow-
parameters. Pellet lot size shall be agreed upon between the
der
seller and the buyer.
C809 Test Methods for Chemical, Mass Spectrometric, and
3.2.4 powder mixture lot—a specified quantity of aluminum
Spectrochemical Analysis of Nuclear-Grade Aluminum
oxideandboroncarbidemadeupofpowdersfromoneormore
Oxide and AluminumOxide-Boron Carbide Composite
sourcesblendedtogethersuchthatsamplestakeninaccordance
Pellets
with Section 7 can be considered as representative of the entire
C859 Terminology Relating to Nuclear Materials
specified quantity.
C1031 Specification for Nuclear-Grade Aluminum Oxide
3.2.5 seller—pellet supplier.
Powder
E11 SpecificationforWovenWireTestSieveClothandTest
4. Technical Requirements
Sieves
4.1 Major Constituents—Aluminum oxide-boron carbide
E105 Practice for Probability Sampling Of Materials
pellets shall be fabricated using major constituents that meet
2.2 ANSI Standard:
the requirements of Specifications C750 and C1031.
ANSI/ASME NQA-1 Quality Assurance Program Require-
3 4.2 Chemical Composition:
ments for Nuclear Facilities
4.2.1 Use analytical chemistry methods in accordance with
2.3 Government Standard:
Methods C809 or demonstrated alternate methods agreed upon
Title 10, Code of Federal Regulations, Energy Part 50
between the buyer and the seller.
4.2.2 The finished pellets shall conform to the following
chemical analysis:
1
This specification is under the jurisdiction of ASTM Committee C26 on
Si 2.0 weight % max
Nuclear Fuel Cycle and is the direct responsibility of Subcommittee C26.03 on
Fe + Cr + Ni 0.6 weight % max
Neutron Absorber Materials Specifications.
Mg 1.0 weight % max
Current edition approved Jan. 1, 2005. Published February 2005. Originally
e1 Na 0.2 weight % max
approved in 1976. Last previous edition approved in 1996 as C784 – 96 . DOI:
Ca 0.3 weight % max
10.1520/C0784-05.
Hf 200 µg/g pellet max
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.
3 4
Available from American National Standards Institute, 11 W. 42nd St., 13th Available from Superintendent of Documents, U.S. Government Printing
Floor, New York, NY 10036. Office, Washington, DC 20402.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959, United States.
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C784 – 05
5.4 Mechanical Properties—Required mechanical proper-
F 50 µg/g pellet max
F + Cl + I + Br 100 µg/g pellet max
ties and test methods shall be mutually agreed upon between
Gd 25 µg/g pellet max
the buyer and the seller.
Sm 50 µg/g pellet max
5.5 Visual Appearance—Visual examination shall be con-
Eu 50 µg/g pellet max
Dy 50 µg/g pellet max
ducted on finished pellets in accordance with Section 7. The
seller and the buyer shall agree on visual standards as repre-
Any elemental impurity not listed in 4.2.2 shall not exceed 1
senting the requirements of 5.5.1, 5.5.2, and 5.5.3. These
weight % as determined by emission spectroscopy. The sum of
standards shall be used as acceptance standards for the visual
all impurities shall not exceed 4.0 weight %. A water-soluble
examination of the
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