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ASTM D 7219 : 2008 : R2014

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

View Superseded by
superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

Standard Specification for Isotropic and Near-isotropic Nuclear Graphites
Available format(s)

Hardcopy , PDF

Superseded date

11-21-2019

Language(s)

English

Published date

05-01-2014

CONTAINED IN VOL. 05.04, 2017 Defines 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.

1.1This 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.

1.2The 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.)

1.3This 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.

Committee
D 02
DocumentType
Standard
Pages
5
ProductNote
Reconfirmed 2014
PublisherName
American Society for Testing and Materials
Status
Superseded
SupersededBy
Supersedes

ASTM C 1783 : 2015 Standard Guide for Development of Specifications for Fiber Reinforced Carbon-Carbon Composite Structures for Nuclear Applications
ASTM D 8075 : 2016 Standard Guide for Categorization of Microstructural and Microtextural Features Observed in Optical Micrographs of Graphite
ASTM D 7301 : 2011 : R2015 Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose
ASTM C 781 : 2018 Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components
ASTM C 1793 : 2015 Standard Guide for Development of Specifications for Fiber Reinforced Silicon Carbide-Silicon Carbide Composite Structures for Nuclear Applications
ASTM D 8093 : 2016 Standard Guide for Nondestructive Evaluation of Nuclear Grade Graphite

ASTM C 1233 : 2015 : REDLINE Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
ASTM D 2638 : 1991 : R1997 Standard Test Method for Real Density of Calcined Petroleum Coke by Helium Pycnometer
ASTM D 2638 : 1991 : R2002 Standard Test Method for Real Density of Calcined Petroleum Coke by Helium Pycnometer
ASTM D 2638 : 2010 : R2015 : EDT 1 Standard Test Method for Real Density of Calcined Petroleum Coke by Helium Pycnometer
ASTM C 1233 : 2003 Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
ASTM C 1233 : 1998 Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
IEEE/ASTM SI_10-2010 American National Standard for Metric Practice
ASTM D 2638 : 2010 Standard Test Method for Real Density of Calcined Petroleum Coke by Helium Pycnometer
ASTM C 1233 : 2015 Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials
ASTM D 2638 : 2006 Standard Test Method for Real Density of Calcined Petroleum Coke by Helium Pycnometer
ASTM C 559 : 2016 : REDLINE Standard Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles
ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
ASTM C 838 : 2016 : REDLINE Standard Test Method for Bulk Density of As-Manufactured Carbon and Graphite Shapes
ASTM C 1233 : 2009 Standard Practice for Determining Equivalent Boron Contents of Nuclear Materials

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