ASTM D7219-19 - 1.11.2019
 
1. Scope

1.1 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.

1.2 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.)

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.

 
2. Referenced Documents

C1233-15(2021)

Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials

D346-25

Standard Practice for Collection and Preparation of Coke Samples for Laboratory Analysis

D2638-24

Standard Test Method for Real Density of Calcined Petroleum Coke by Helium Pycnometer

IEEE/ASTM SI 10

American National Standard for Use of the International System of Units (SI): The Modern Metric System

C838-16(2023)

Standard Test Method for Bulk Density of As-Manufactured Carbon and Graphite Shapes

NQA-1

Quality Assurance Program Requirements for Nuclear Facilities Available from American Society of Mechanical Engineers (ASME), ASME International Headquarters, Three Park Ave., New York, NY 10016-5990.

C781-20

Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components

C559-16(2020)

Standard Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles

C709-09

Standard Terminology Relating to Manufactured Carbon and Graphite (Withdrawn 2017)