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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.
This abstract is a brief summary of the referenced standard. It is informational only and not an official part of the standard; the full text of the standard itself must be referred to for its use and application. ASTM does not give any warranty express or implied or make any representation that the contents of this abstract are accurate, complete or up to date.
Significance and Use
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.
2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.
C559 Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles
C750 Specification for Nuclear-Grade Boron Carbide Powder
C809 Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and AluminumOxide-Boron Carbide Composite Pellets
C859 Terminology Relating to Nuclear Materials
C1031 Specification for Nuclear-Grade Aluminum Oxide Powder
E11 Specification for Woven Wire Test Sieve Cloth and Test Sieves
E105 Practice for Probability Sampling of Materials
ANSI StandardANSI/ASMENQA-1 Quality Assurance Program Requirements for Nuclear Facilities Available from American National Standards Institute, 11 W. 42nd St., 13th Floor, New York, NY 10036.
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology); 71.060.50 (Salts)
UNSPSC Code 26142106(Nuclear reactor control rod systems)