ASTM D7219-08(2014)

Standard Specification for Isotropic and Near-isotropic Nuclear Graphites

STANDARD published on 1.5.2014

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The information about the standard:

Designation standards: ASTM D7219-08(2014)
Note: WITHDRAWN
Publication date standards: 1.5.2014
SKU: NS-37903
The number of pages: 5
Approximate weight : 15 g (0.03 lbs)
Country: American technical standard
Category: Technical standards ASTM

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The category - similar standards:

Fissile materials

Annotation of standard text ASTM D7219-08(2014) :

Keywords:

chemical properties, mechanical properties, nuclear graphite, physical properties, processing, ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)

Additional information

1. Scope

1.1 This specification covers the classification, processing, and properties of nuclear grade graphite billets with dimensions sufficient to meet the designer’s requirements for fuel elements, moderator or reflector blocks, in a high temperature gas cooled reactor. The graphite classes specified here would be suitable for reactor core applications where neutron irradiation induced dimensional changes are a significant design consideration.

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 and health practices and determine the applicability of regulatory limitations prior to use.

2. Referenced Documents

C1233-15(2021)	Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
D346-04	Standard Practice for Collection and Preparation of Coke Samples for Laboratory Analysis
D2638-21	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)

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