ASTM D7219-19
(Specification)Standard Specification for Isotropic and Near-isotropic Nuclear Graphites
Standard Specification for Isotropic and Near-isotropic Nuclear Graphites
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.
General Information
- Status
- Published
- Publication Date
- 31-Oct-2019
- Technical Committee
- D02 - Petroleum Products, Liquid Fuels, and Lubricants
- Drafting Committee
- D02.F0 - Manufactured Carbon and Graphite Products
Relations
- Replaces
ASTM D7219-08(2014) - Standard Specification for Isotropic and Near-isotropic Nuclear Graphites - Effective Date
- 01-Nov-2019
- Refers
ASTM D4175-23a - Standard Terminology Relating to Petroleum Products, Liquid Fuels, and Lubricants - Effective Date
- 15-Dec-2023
- Effective Date
- 01-Dec-2023
- Refers
ASTM D4175-23e1 - Standard Terminology Relating to Petroleum Products, Liquid Fuels, and Lubricants - Effective Date
- 01-Jul-2023
- Effective Date
- 01-Jun-2020
- Effective Date
- 01-May-2020
- Effective Date
- 01-Nov-2019
- Effective Date
- 01-Oct-2018
- Effective Date
- 01-Jan-2016
- Refers
ASTM C838-16 - Standard Test Method for Bulk Density of As-Manufactured Carbon and Graphite Shapes - Effective Date
- 01-Jan-2016
- Effective Date
- 01-May-2014
- Effective Date
- 01-May-2010
- Effective Date
- 01-May-2010
- Effective Date
- 01-May-2010
- Effective Date
- 01-May-2010
Overview
ASTM D7219-19 - Standard Specification for Isotropic and Near-isotropic Nuclear Graphites specifies the classification, manufacturing, processing, and properties of as-manufactured nuclear grade graphite billets. These graphites are designed for core structural components, including fuel elements, moderator, and reflector blocks in high temperature gas-cooled nuclear reactors. The standard ensures that isotropic and near-isotropic graphites meet rigorous performance criteria, particularly where dimensional stability under neutron irradiation is critical. All requirements are stipulated in SI units.
Key Topics
Classification and Properties
- Defines classes of nuclear graphites (isotropic, near-isotropic; high purity, low purity)
- Outlines grain size categories (medium, fine, superfine, ultrafine, microfine)
- Provides ranges for key physical and mechanical properties, such as coefficient of thermal expansion, thermal conductivity, density, and strength
Manufacturing and Materials
- Specifies requirements for raw materials (fillers must be derived from petroleum or coal tar cokes with measured thermal expansion)
- Details binder and impregnant criteria for traceability and uniformity (must be traceable by lot and grade)
- Allows for use of recycled material under controlled conditions
Processing and Traceability
- Includes requirements for forming techniques (extrusion, molding, iso-molding)
- Mandates traceability of each billet to its formulation, raw material batch, forming lot, and key processing steps
- Outlines lot-based sampling and testing for validation
Quality Assurance
- Requires compliance with ASME NQA-1 quality assurance programs, or other purchaser-specified requirements
- Stipulates certification and permanent marking of each billet for quality control and traceability
Impurity Control
- Sets limits on ash content and boron equivalent for nuclear purity classes
- Recommends measurement and reporting of specific chemical impurities relevant for neutron absorption and reactor performance
Applications
Nuclear Reactor Components
- Design and fabrication of fuel elements, moderator, and reflector blocks in high temperature gas-cooled reactors
- Service environments where stability under neutron irradiation and high temperature is essential
Quality-Controlled Manufacturing
- Suppliers producing nuclear-grade graphite products to strict standards for mechanical and chemical properties
- Applications requiring documented traceability, quality assurance, and conformity to international nuclear safety codes
Material Qualification and Specification
- Reactor designers and engineers specifying materials that provide verifiable dimensional and mechanical stability during operation
- Evaluating graphite for core components where impurity levels and irradiation response are crucial factors
Related Standards
- ASTM C559: Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles
- ASTM C781: Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components
- ASTM C838: Test Method for Bulk Density of As-Manufactured Carbon and Graphite Shapes
- ASTM C1233: Practice for Determining Equivalent Boron Contents of Nuclear Materials
- ASTM D346: Practice for Collection and Preparation of Coke Samples for Laboratory Analysis
- ASTM D2638: Test Method for Real Density of Calcined Petroleum Coke by Helium Pycnometer
- IEEE/ASTM SI 10: Use of the International System of Units (SI)
- ASME NQA-1: Quality Assurance Program Requirements for Nuclear Facilities
Keywords: ASTM D7219, isotropic nuclear graphite, near-isotropic graphite, nuclear-grade graphite, high temperature reactor, core graphite, reactor moderator, reflector blocks, graphite manufacturing, quality assurance, graphite properties, impurity control, ASME NQA-1, traceability, nuclear safety standards.
For compliance, nuclear engineers and graphite manufacturers should refer directly to ASTM D7219-19 for complete technical details and consult related standards as referenced.
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Frequently Asked Questions
ASTM D7219-19 is a technical specification published by ASTM International. Its full title is "Standard Specification for Isotropic and Near-isotropic Nuclear Graphites". This standard covers: 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.
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.
ASTM D7219-19 is classified under the following ICS (International Classification for Standards) categories: 27.120.30 - Fissile materials and nuclear fuel technology. The ICS classification helps identify the subject area and facilitates finding related standards.
ASTM D7219-19 has the following relationships with other standards: It is inter standard links to ASTM D7219-08(2014), ASTM D4175-23a, ASTM C838-16(2023), ASTM D4175-23e1, ASTM C781-20, ASTM C559-16(2020), ASTM C781-19, ASTM C781-18, ASTM C559-16, ASTM C838-16, ASTM C781-08(2014), ASTM D2638-10, ASTM C559-90(2010), ASTM C838-96(2010)e1, ASTM D346-04(2010). Understanding these relationships helps ensure you are using the most current and applicable version of the standard.
ASTM D7219-19 is available in PDF format for immediate download after purchase. The document can be added to your cart and obtained through the secure checkout process. Digital delivery ensures instant access to the complete standard document.
Standards Content (Sample)
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.
Designation:D7219 −19
Standard Specification for
Isotropic and Near-isotropic Nuclear Graphites
This standard is issued under the fixed designation D7219; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope* C1233Practice for Determining Equivalent Boron Contents
of Nuclear Materials
1.1 This specification covers the classification, processing,
D346 Practice for Collection and Preparation of Coke
andtypicalpropertiesofas-manufacturednucleargradegraph-
Samples for Laboratory Analysis
ite billets with dimensions sufficient to meet the designer’s
D2638Test Method for Real Density of Calcined Petroleum
requirements for fuel elements, moderator or reflector blocks,
Coke by Helium Pycnometer
in a high temperature reactor. The graphite classes specified
D4175Terminology Relating to Petroleum Products, Liquid
here may be suitable for reactor core applications where
Fuels, and Lubricants
dimensional change due to fast neutron irradiation has a
IEEE/ASTM SI 10American National Standard for Use of
significant impact on design, provided they meet the require-
theInternationalSystemofUnits(SI):TheModernMetric
ments of the ASME code.
System
1.2 The values stated in SI units are to be regarded as
2.2 ASME Standard:
standard. No other units of measurement are included in this
NQA-1 Quality Assurance Program Requirements for
standard. (See IEEE/ASTM SI 10.)
Nuclear Facilities, Sec III Div 5 Sub Sect HH sub-partA:
1.3 This standard does not purport to address all of the
Graphite Materials (HHA)
safety concerns, if any, associated with its use. It is the
3. Terminology
responsibility of the user of this standard to establish appro-
priate safety, health, and environmental practices and deter-
3.1 Definitions—Definitionsrelatingtothisspecificationare
mine the applicability of regulatory limitations prior to use.
given in Terminology D4175.
1.4 This international standard was developed in accor-
3.2 Definitions of Terms Specific to This Standard:
dance with internationally recognized principles on standard-
3.2.1 baking/re-baking charge, n—in carbon and graphite
ization established in the Decision on Principles for the
technology, number of billets in a baking/re-baking furnace
Development of International Standards, Guides and Recom-
run.
mendations issued by the World Trade Organization Technical
3.2.2 bulk density, n—in carbon and graphite technology,
Barriers to Trade (TBT) Committee.
mass of a unit volume of material including both permeable
2. Referenced Documents and impermeable voids.
3.2.3 extrusion forming lot, n—in carbon and graphite
2.1 ASTM Standards:
technology, number of billets of the same size extruded in an
C559Test Method for Bulk Density by Physical Measure-
uninterrupted sequence.
ments of Manufactured Carbon and Graphite Articles
C781PracticeforTestingGraphiteMaterialsforGas-Cooled
3.2.4 grain, n—in manufactured carbon and graphite, par-
Nuclear Reactor Components
ticle of filler material (usually coke or graphite) in the starting
C838Test Method for Bulk Density of As-Manufactured
mix formulation; also referred to as granular material, filler
Carbon and Graphite Shapes
particle,oraggregatematerial;thetermisalsousedtodescribe
the general texture of a carbon or graphite body, as in the
descriptions listed below:
This specification is under the jurisdiction of ASTM Committee D02 on
3.2.4.1 coarse grained, adj—containing grains in the start-
Petroleum Products, Liquid Fuels, and Lubricants and is the direct responsibility of
ing mix that are substantially greater than 4 mm in size.
Subcommittee D02.F0 on Manufactured Carbon and Graphite Products.
Current edition approved Nov. 1, 2019. Published November 2019. Originally
3.2.4.2 medium coarse grained, adj—containing grains in
approved in 2005. Last previous edition approved in 2014 as D7219–08 (2014).
the starting mix that are generally less than 4 mm in size.
DOI: 10.1520/D7219-19.
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on Available from American Society of Mechanical Engineers (ASME), ASME
the ASTM website. International Headquarters, Two Park Ave., New York, NY 10016-5990.
*A Summary of Changes section appears at the end of this standard
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
D7219−19
TABLE 1 ASTM Standard Classes of Nuclear Graphite
Purity
B C
A CTE Isotropy Ratio Bulk Density,
Class D Class Designation
Boron Equivalent,
(α /α ) g/cm (min)
AG WG
ppm (max)
Isomolded, isotropic—High Purity 1.0-1.1 2 1.7 IIHP
Isomolded, isotropic—Low Purity 1.0-1.1 10 1.7 IILP
Isomolded, near-isotropic—High Purity 1.1-1.15 2 1.7 INHP
Isomolded, near-isotropic—Low Purity 1.1-1.15 10 1.7 INLP
Extruded, isotropic—High Purity 1.0-1.1 2 1.7 EIHP
Extruded, isotropic—Low Purity 1.0-1.1 10 1.7 EILP
Extruded, near-isotropic—High Purity 1.1-1.15 2 1.7 ENHP
Extruded, near-isotropic—Low Purity 1.1-1.15 10 1.7 ENLP
Molded, isotropic—High Purity 1.0-1.1 2 1.7 MIHP
Molded, isotropic—Low Purity 1.0-1.1 10 1.7 MILP
Molded, near-isotropic—High Purity 1.1-1.15 2 1.7 MNHP
Molded, near-isotropic—Low Purity 1.1-1.15 10 1.7 MNLP
A
These classes may be further modified by the grain size.
B
Determined in accordance with Practice C781.
C
Determined in accordance with Test Method C559.
D
Determined in accordance with Practice C1233.
3.2.4.3 medium grained, adj—containing grains in the start- 3.2.12 impregnation charge, n—in carbon and graphite
ing mix that are generally less than 2 mm in size. technology, number of billets in an autoclave cycle.
3.2.4.4 medium fine grained, adj—containing grains in the
3.2.13 isotropic nuclear graphite, n—graphite in which the
starting mix that are generally less than 1 mm in size.
isotropy ratio based on the coefficient of thermal expansion is
3.2.4.5 fine grained, adj—containing grains in the starting 1.00 to 1.10.
mix that are less than 100 µm in size.
3.2.14 low purity nuclear graphite, n—in carbon and
3.2.4.6 superfine grained, adj—containing grains in the
graphite technology, nuclear graphite with an Equivalent
starting mix that are less than 50 µm in size.
Boron Content greater than 2 ppm but less than 10 ppm.
3.2.4.7 ultrafine grained, adj—containinggrainsinthestart-
3.2.15 mix formulation, n—percentages of each specifically
ing mix that are less than 10 µm in size.
sized filler used to manufacture a graphite grade.
3.2.4.8 microfine grained, adj—containing grains in the
3.2.16 molding forming lot, n—in carbon and graphite
starting mix that are less than 2 µm in size.
technology, number of billets molded from a molding powder
3.2.5 green batch, n—in carbon and graphite technology,
lot.
mass of coke, recycle green mix, recycle graphite, and pitch
3.2.17 molding powder lot, n—sufficient quantity of re-
that is required to produce a forming lot.
milled and blended green batch produced from an uninter-
3.2.6 green mix, n—in carbon and graphite technology,
rupted flow of raw materials, or produced in a sequence of
percentageofmixformulation,pitchandadditivesrequiredfor
identical materials batches, to produce a molding forming lot.
the forming lot, which is processed and ready to be formed.
3.2.18 near isotropic nuclear graphite, n—in carbon and
3.2.7 graphite billet, n—in carbon and graphite technology,
extruded, molded, or iso-molded graphite artifact with dimen- graphite technology, graphite in which the isotropy ratio based
sions sufficient to meet the designer’s requirements for reactor
on the coefficient of thermal expansion is 1.10 to 1.15.
components.
3.2.19 nuclear graphite class, n—in carbon and graphite
3.2.8 graphite grade, n—in carbon and graphite
technology, designation of a nuclear graphite based upon its
technology, designation given to a material by a manufacturer
forming method, isotropy, purity and density (see Table 1).
such that it is always reproduced to the same specification and
3.2.20 production lot, n—in carbon and graphite
from the same raw materials and mix formulation.
technology, specified number of billets made in accordance
3.2.9 graphitization charge, n—in carbon and graphite
with this specification and additional requirements determined
technology, number of billets of the same grade in a graphi-
by the purchaser.
tizing furnace run.
3.2.21 purification charge, n—in carbon and graphite
3.2.10 graphitizing furnace run, n—in carbon and graphite
technology, number of billets in a purification run.
technology, total number of billets graphitized together in one
graphitization furnace.
3.2.22 recycle green mix, n—in carbon and graphite
3.2.11 high purity nuclear graphite, n—in carbon and technology, ground non-baked billets or non used green mix
manufactured in compliance with the mix formulation speci-
graphite technology, nuclear graphite with an Equivalent
Boron Content less than 2 ppm. fied here.
D7219−19
TABLE 2 Inspection Sampling and Testing of Filler Cokes
Inspection Plan Sampling Procedure Tests and Test Methods
A representative sample of the Sample in accordance with Practice D346 The procedure in Practice C781 shall be used to
coke shall be taken prior to the 1. A sufficient sample for preparation of CTE test prepare test specimens for the measurement of
mixing step of manufacture specimens coke CTE.
2. A sufficient sample will be taken for additional Measure the coke real density in accordance with
testing. This sample shall be retained for a pe- Test Method D2638.
riod specified by the graphite purchaser
4. Significance and Use 5.6.2 Forming—The green mix may be formed by
extrusion, molding (including vibrationally molding), or iso-
4.1 Purpose—The purpose of this specification is to docu-
molding.
mentthetypicalpropertiesofas-manufacturednucleargraphite
5.6.3 Graphitization Temperature—The graphitization tem-
and levels of quality assurance and traceability for isotropic
perature shall be determined on each billet using the procedure
and near-isotropic nuclear grade graphites. The properties
described in Practice C781. Each billet tested in accordance
which are considered suitable for the application will depend
with Practice C781 shall have a Specific Electrical Resistivity
on the design requirements and on the range of materials that
(SER) corresponding to a graphitization temperature of at least
can be available from the manufacturer.
2700°C.
5. Materials and Manufacture
6. Chemical Properties
5.1 Nuclear Graphite Classes—See Table 1.
6.1 Each graphite production lot shall be sampled in accor-
5.2 Raw Materials:
dancewithSection11.Thechemicalimpuritiestobemeasured
5.2.1 Fillers:
shall be as agreed between the supplier and the purchaser. The
5.2.1.1 The filler shall consist of a near-isotropic or isotro-
minimumlistofelementstobemeasuredandusedfortheEBC
pic coke derived from a petroleum oil or coal tar.
calculation shall be B, Cd, Dy, Eu, Gd, and Sm.
5.2.1.2 The coke shall have a coefficient of linear thermal
6.2 The boron equivalent shall be calculated in accord
...
This document is not an ASTM standard and is intended only to provide the user of an ASTM standard an indication of what changes have been made to the previous version. Because
it may not be technically possible to adequately depict all changes accurately, ASTM recommends that users consult prior editions as appropriate. In all cases only the current version
of the standard as published by ASTM is to be considered the official document.
Designation: D7219 − 08 (Reapproved 2014) D7219 − 19 An American National Standard
Standard Specification for
Isotropic and Near-isotropic Nuclear Graphites
This standard is issued under the fixed designation D7219; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision. A number in parentheses indicates the year of last reapproval. A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1. Scope 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 gas cooled reactor. The graphite classes specified here wouldmay be suitable for reactor core applications where
neutron irradiation induced dimensional changes are a significant design consideration.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 safety, health, and healthenvironmental 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
2.1 ASTM Standards:
C559 Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles
C709 Terminology Relating to Manufactured Carbon and Graphite (Withdrawn 2017)
C781 Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components
C838 Test Method for Bulk Density of As-Manufactured Carbon and Graphite Shapes
C1233 Practice for Determining Equivalent Boron Contents of Nuclear Materials
D346 Practice for Collection and Preparation of Coke Samples for Laboratory Analysis
D2638 Test Method for Real Density of Calcined Petroleum Coke by Helium Pycnometer
D4175 Terminology Relating to Petroleum Products, Liquid Fuels, and Lubricants
IEEE/ASTM SI 10 American National Standard for Use of the International System of Units (SI): The Modern Metric System
2.2 ASME Standard:
NQA-1 Quality Assurance Program Requirements for Nuclear FacilitiesFacilities, Sec III Div 5 Sub Sect HH sub-part A:
Graphite Materials (HHA)
3. Terminology
3.1 Definitions—Definitions relating to this specification are given in Terminology C709D4175.
3.2 Definitions of Terms Specific to This Standard:
3.2.1 baking/re-baking charge—charge, n—in carbon and graphite technology, number of billets in a baking/re-baking furnace
run.
This specification is under the jurisdiction of ASTM Committee D02 on Petroleum Products, Liquid Fuels, and Lubricants and is the direct responsibility of Subcommittee
D02.F0 on Manufactured Carbon and Graphite Products.
Current edition approved May 1, 2014Nov. 1, 2019. Published July 2014November 2019. Originally approved in 2005. Last previous edition approved in 20082014 as
D7219 – 08.D7219 – 08 (2014). DOI: 10.1520/D7219-08R14. 10.1520/D7219-19.
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at service@astm.org. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
Available from American Society of Mechanical Engineers (ASME), ASME International Headquarters, ThreeTwo Park Ave., New York, NY 10016-5990.
*A Summary of Changes section appears at the end of this standard
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
D7219 − 19
3.2.2 bulk density—density, n—in carbon and graphite technology, mass of a unit volume of material including both permeable
and impermeable voids.
3.2.3 extrusion forming lot—lot, n—in carbon and graphite technology, number of billets of the same size extruded in an
uninterrupted sequence.
3.2.4 grain, n—in manufactured carbon and graphite, particle of filler material (usually coke or graphite) in the starting mix
formulation; also referred to as granular material, filler particle, or aggregate material; the term is also used to describe the general
texture of a carbon or graphite body, as in the descriptions listed below:
3.2.4.1 coarse grained, adj—containing grains in the starting mix that are substantially greater than 4 mm in size.
3.2.4.2 medium coarse grained, adj—containing grains in the starting mix that are generally less than 4 mm in size.
3.2.4.3 medium grained, adj—containing grains in the starting mix that are generally less than 2 mm in size.
3.2.4.4 medium fine grained, adj—containing grains in the starting mix that are generally less than 1 mm in size.
3.2.4.5 fine grained, adj—containing grains in the starting mix that are less than 100 μm in size.
3.2.4.6 superfine grained, adj—containing grains in the starting mix that are less than 50 μm in size.
3.2.4.7 ultrafine grained, adj—containing grains in the starting mix that are less than 10 μm in size.
3.2.4.8 microfine grained, adj—containing grains in the starting mix that are less than 2 μm in size.
3.2.5 green batch—batch, n—in carbon and graphite technology, mass of coke, recycle green mix, recycle graphite, and pitch
that is required to produce a forming lot.
3.2.6 green mix—mix, n—in carbon and graphite technology, percentage of mix formulation, pitch and additives required for
the forming lot, which is processed and ready to be formed.
3.2.7 graphite billet—billet, n—in carbon and graphite technology, extruded, molded, or iso-molded graphite artifact with
dimensions sufficient to meet the designer’s requirements for reactor components.
3.2.8 graphite grade—grade, n—in carbon and graphite technology, designation given to a material by a manufacturer such that
it is always reproduced to the same specification and from the same raw materials and mix formulation.
3.2.9 graphitization charge—charge, n—in carbon and graphite technology, number of billets of the same grade in a
graphitizing furnace run.
3.2.10 graphitizing furnace run—run, n—in carbon and graphite technology, total number of billets graphitized together in one
graphitization furnace.
3.2.11 high purity nuclear graphite—graphite, n—in carbon and graphite technology, nuclear graphite with an Equivalent
Boron Content less than 2 ppm.
3.2.12 impregnation charge—charge, n—in carbon and graphite technology, number of billets in an autoclave cycle.
3.2.13 isotropic nuclear graphite—graphite, n—graphite in which the isotropy ratio based on the coefficient of thermal
expansion is 1.00 to 1.10.
3.2.14 low purity nuclear graphite—graphite, n—in carbon and graphite technology, nuclear graphite with an Equivalent Boron
Content greater than 2 ppm but less than 10 ppm.
3.2.15 mix formulation—formulation, n—percentages of each specifically sized filler used to manufacture a graphite grade.
3.2.16 molding forming lot—lot, n—in carbon and graphite technology, number of billets molded from a molding powder lot.
3.2.17 molding powder lot—lot, n—sufficient quantity of re-milled and blended green batch produced from an uninterrupted
flow of raw materials, or produced in a sequence of identical materials batches, to produce a molding forming lot.
3.2.18 near isotropic nuclear graphite—graphite, n—graphite in carbon and graphite technology, graphite in which the
isotropy ratio based on the coefficient of thermal expansion is 1.10 to 1.15.
3.2.19 nuclear graphite class—class, n—in carbon and graphite technology, designation of a nuclear graphite based upon its
forming method, isotropy, purity and density (see Table 1).
3.2.20 production lot—lot, n—in carbon and graphite technology, specified number of billets made in accordance with this
specification and additional requirements determined by the purchaser.
3.2.21 purification charge—charge, n—in carbon and graphite technology, number of billets in a purification run.
3.2.22 recycle green mix—mix, n—in carbon and graphite technology, ground non-baked billets or non used green mix
manufactured in compliance with the mix formulation specified here.
4. Significance and Use
4.1 Purpose—The purpose of this specification is to document the minimum acceptable properties typical properties of
as-manufactured nuclear graphite and levels of quality assurance and traceability for isotropic and near-isotropic nuclear grade
D7219 − 19
TABLE 1 ASTM Standard Classes of Nuclear Graphite
Purity
B C
A CTE Isotropy Ratio Bulk Density,
Class B Class Designation
Ash Content, Boron Equivalent,
(α /α ) g/cm (min)
AG WG
ppm (max) ppm (max)
Isomolded, isotropic—High Purity 1.0-1.1 300 2 1.7 IIHP
Isomolded, isotropic—High Purity 1.0-1.1 2 1.7 IIHP
Isomolded, isotropic—Low Purity 1.0-1.1 1000 10 1.7 IILP
Isomolded, isotropic—Low Purity 1.0-1.1 10 1.7 IILP
Isomolded, near-isotropic—High Purity 1.1-1.15 300 2 1.7 INHP
Isomolded, near-isotropic—High Purity 1.1-1.15 2 1.7 INHP
Isomolded, near-isotropic—Low Purity 1.1-1.15 1000 10 1.7 INLP
Isomolded, near-isotropic—Low Purity 1.1-1.15 10 1.7 INLP
Extruded, isotropic—High Purity 1.0-1.1 300 2 1.7 EIHP
Extruded, isotropic—High Purity 1.0-1.1 2 1.7 EIHP
Extruded, isotropic—Low Purity 1.0-1.1 1000 10 1.7 EILP
Extruded, isotropic—Low Purity 1.0-1.1 10 1.7 EILP
Extruded, near-isotropic—High Purity 1.1-1.15 300 2 1.7 ENHP
Extruded, near-isotropic—High Purity 1.1-1.15 2 1.7 ENHP
Extruded, near-isotropic—Low Purity 1.1-1.15 1000 10 1.7 ENLP
Extruded, near-isotropic—Low Purity 1.1-1.15 10 1.7 ENLP
Molded, isotropic—High Purity 1.0-1.1 300 2 1.7 MIHP
Molded, isotropic—High Purity 1.0-1.1 2 1.7 MIHP
Molded, isotropic—Low Purity 1.0-1.1 1000 10 1.7 MILP
Molded, isotropic—Low Purity 1.0-1.1 10 1.7 MILP
Molded, near-isotropic—High Purity 1.1-1.15 300 2 1.7 MNHP
Molded, near-isotropic—High Purity 1.1-1.15 2 1.7 MNHP
Molded, near-isotropic—Low Purity 1.1-1.15 1000 10 1.7 MNLP
Molded, near-isotropic—Low Purity 1.1-1.15 10 1.7 MNLP
A
These classes may be further modified by the grain size as defined in Terminology size.C709 (see Table 2).
B
Determined in accordance with Practice C781.
C
Determined in accordance with Test Method C559.
D
Determined in accordance with Practice C1233.
graphites. The properties which are considered suitable for the application will depend on the design requirements and on the range
of materials that can be available from the manufacturer.
5. Materials and Manufacture
5.1 Nuclear Graphite Classes—See Table 1.
5.2 Raw Materials:
5.2.1 Fillers:
5.2.1.1 The filler shall consist of a near-isotropic or isotropic coke derived from a petroleum oil or coal tar.
5.2.1.2 The coke shall have a coefficient of linear thermal expansion (CTE), determined in accordance with Practice C781 and
-6 -1 -6 -1
measured over the temperature range 2525 °C to 500°C,500 °C, of between 3.5 × 10 °C and 5.5 × 10 °C .
5.2.1.3 The coke shall be sampled and distributed as described in Table 32.
5.2.1.4 Graphite manufactured in compliance with this specification but failing to meet the property requirements of Sections
6 and 7 may be used as recycle material in the mix formulation.
5.2.1.5 Recycle green mix manufactured from raw materials in compliance with this specification may be used in the mix
formulation.
5.2.1.6 The maximum filler particle size used in the mix formulation shall be 1.68 mm.
5.3 Binder—The binder(s) shall consist of coal tar pitch of the same grade from the same manufacturer. The specific binder(s)
used shall be identified to the purchaser and be traceable through the forming lot.
5.4 Impregnant—The impregnant(s) shall consist of a petroleum or coal tar pitch of the same grade from the same manufacturer.
The specific impregnant used shall be identified to the purchaser and be traceable through the impregnation steps.
5.5 Manufacturing or Processing Additives—Additives (for example, extrusion aids) may
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