Standard Specification for Isotropic and Near-isotropic Nuclear Graphites
|Publication Date:||1 November 2019|
|ICS Code (Fissile materials and nuclear fuel technology):||27.120.30|
This specification covers the classification, processing, and typical properties of as-manufactured nuclear grade graphite billets with dimensions sufficient to meet the designer's requirements for fuel elements, moderator or reflector blocks, in a high temperature reactor. The graphite classes specified here may be suitable for reactor core applications where dimensional change due to fast neutron irradiation has a significant impact on design, provided they meet the requirements of the ASME code.
The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. (See IEEE/ASTM SI 10.)
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.
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.
*A Summary of Changes section appears at the end of this standard