ASTM D7301-21

Standard Specification for Nuclear Graphite Suitable for Components Subjected to Low Neutron Irradiation Dose

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 reflector blocks and core support structures, 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 not a significant design consideration.  
1.2 The purpose of this specification is to document the minimum acceptable properties and levels of quality assurance and traceability for nuclear grade graphite suitable for components subjected to low irradiation dose. Nuclear graphites meeting the requirements of Specification D7219 are also suitable for components subjected to low neutron irradiation dose.  
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
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-2021
• ICS: 27.120.20 - Nuclear power plants. Safety
• Technical Committee: D02 - Petroleum Products, Liquid Fuels, and Lubricants
• Drafting Committee: D02.F0 - Manufactured Carbon and Graphite Products

Relations

• Refers: ASTM C781-20 - Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components
• Effective Date: 01-Jun-2020

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:D7301 −21
Standard Specification for
Nuclear Graphite Suitable for Components Subjected to
1
Low Neutron Irradiation Dose
This standard is issued under the fixed designation D7301; 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* C838Test Method for Bulk Density of As-Manufactured
Carbon and Graphite Shapes
1.1 This specification covers the classification, processing,
C1233Practice for Determining Equivalent Boron Contents
and properties of nuclear grade graphite billets with dimen-
of Nuclear Materials
sions sufficient to meet the designer’s requirements for reflec-
D346 Practice for Collection and Preparation of Coke
tor blocks and core support structures, in a high temperature
Samples for Laboratory Analysis
gas cooled reactor. The graphite classes specified here would
D2638Test Method for Real Density of Calcined Petroleum
be suitable for reactor core applications where neutron irradia-
Coke by Helium Pycnometer
tion induced dimensional changes are not a significant design
D4175Terminology Relating to Petroleum Products, Liquid
consideration.
Fuels, and Lubricants
1.2 The purpose of this specification is to document the
D7219 Specification for Isotropic and Near-isotropic
minimum acceptable properties and levels of quality assurance
Nuclear Graphites
and traceability for nuclear grade graphite suitable for compo-
D8186Test Method for Measurement of Impurities in
nents subjected to low irradiation dose. Nuclear graphites
Graphite by Electrothermal Vaporization Inductively
meeting the requirements of Specification D7219 are also
Coupled Plasma Optical Emission Spectrometry (ETV-
suitable for components subjected to low neutron irradiation
ICP OES)
dose.
IEEE/ASTM SI 10 American National Standard for Use of
theInternationalSystemofUnits(SI):TheModernMetric
1.3 The values stated in SI units are to be regarded as
standard. No other units of measurement are included in this System
3
standard.
2.2 ASME Standards:
1.4 This international standard was developed in accor- NQA-1 Quality Assurance Program Requirements for
dance with internationally recognized principles on standard-
Nuclear Facilities
ization established in the Decision on Principles for the
Development of International Standards, Guides and Recom-
3. Terminology
mendations issued by the World Trade Organization Technical
3.1 Definitions—Definitionsrelatingtothisspecificationare
Barriers to Trade (TBT) Committee.
given in Terminology D4175. See Table 1.
3.2 Definitions of Terms Specific to This Standard:
2. Referenced Documents
3.2.1 anistropic nuclear graphite, n—graphite in which the
2
2.1 ASTM Standards:
isotropy ratio based on the coefficient of thermal expansion is
C561Test Method for Ash in a Graphite Sample
greater than 1.15.
C781PracticeforTestingGraphiteMaterialsforGas-Cooled
3.2.2 baking/re-baking charge, n—number of billets in a
Nuclear Reactor Components
baking/re-baking furnace run.
3.2.3 bulk density, n—mass of a unit volume of material
1 including both permeable and impermeable voids.
This specification is under the jurisdiction of ASTM Committee D02 on
Petroleum Products, Liquid Fuels, and Lubricants and is the direct responsibility of
3.2.4 extrusion forming lot, n—number of billets of the
Subcommittee D02.F0 on Manufactured Carbon and Graphite Products.
same size extruded in an uninterrupted sequence.
Current edition approved Nov. 1, 2021. Published November 2021. Originally
approved in 2008. Last previous edition approved in 2015 as D7301–11 (2015).
DOI: 10.1520/D7301-21.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or
3
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM Available from American Society of Mechanical Engineers (ASME), ASME
Standards volume information, refer to the standard’s Document Summary page on International Headquarters, Two Park Ave., New York, NY 10016-5990, http://
the ASTM website. www.asme.org.
*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
1

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D7301−21
TABLE 1 ASTM Graphite Grain Size Definitions from Terminology
3.2.15 isotropy ratio, n—in carbon and graphite
D4175
technology, ratio of a given property value in the against grain
Graphite Definition of Grains in
direction to its corresponding value in
...

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: D7301 − 11 (Reapproved 2015) D7301 − 21
Standard Specification for
Nuclear Graphite Suitable for Components Subjected to
1
Low Neutron Irradiation Dose
This standard is issued under the fixed designation D7301; 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 properties of nuclear grade graphite billets with dimensions
sufficient to meet the designer’s requirements for reflector blocks and core support structures, 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 not a significant design consideration.
1.2 The purpose of this specification is to document the minimum acceptable properties and levels of quality assurance and
traceability for nuclear grade graphite suitable for components subjected to low irradiation dose. Nuclear graphites meeting the
requirements of Specification D7219 are also suitable for components subjected to low neutron irradiation dose.
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.
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
2.1 ASTM Standards:
C559C561 Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite ArticlesAsh in a
Graphite Sample
3
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
D7219 Specification for Isotropic and Near-isotropic Nuclear Graphites
D8186 Test Method for Measurement of Impurities in Graphite by Electrothermal Vaporization Inductively Coupled Plasma
Optical Emission Spectrometry (ETV-ICP OES)
1
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 June 1, 2015Nov. 1, 2021. Published July 2015November 2021. Originally approved in 2008. Last previous edition approved in 20112015 as
D7301 – 11.D7301 – 11 (2015). DOI: 10.1520/D7301-11R15.10.1520/D7301-21.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM Standards
volume information, refer to the standard’s Document Summary page on the ASTM website.
*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
1

---------------------- Page: 1 ----------------------
D7301 − 21
IEEE/ASTM SI 10 American National Standard for Use of the International System of Units (SI): The Modern Metric System
3
2.2 ASME Standards:
NQA-1 Quality Assurance Program Requirements for Nuclear Facilities
3. Terminology
3.1 Definitions—Definitions relating to this specification are given in Terminology C709D4175. See Table 1.
3.2 Definitions of Terms Specific to This Standard:
3.2.1 anistropic nuclear graphite, n—graphite in which the isotropy ratio based on the coefficient of thermal expansion is greater
than 1.15.
3.2.2 baking/re-baking charge, n—number of billets in a baking/re-baking furnace run.
3.2.3 bulk density, n—mass of a unit volume of material including both permeable and impermeable voids.
3.2.4 extrusion forming lot, n—number of billets of the same size extruded in an uninterrupted sequence.
3.2.5 gre
...