ASTM D7301-11(2015)

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.

General Information

• Status: Historical
• Publication Date: 31-May-2015
• 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

Standards Content (Sample)

NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
Designation:D7301 −11 (Reapproved 2015)
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 C1233Practice for Determining Equivalent Boron Contents
of Nuclear Materials
1.1 This specification covers the classification, processing,
D346Practice for Collection and Preparation of Coke
and properties of nuclear grade graphite billets with dimen-
Samples for Laboratory Analysis
sions sufficient to meet the designer’s requirements for reflec-
D2638Test Method for Real Density of Calcined Petroleum
tor blocks and core support structures, in a high temperature
Coke by Helium Pycnometer
gas cooled reactor. The graphite classes specified here would
D7219 Specification for Isotropic and Near-isotropic
be suitable for reactor core applications where neutron irradia-
Nuclear Graphites
tion induced dimensional changes are not a significant design
IEEE/ASTM SI 10 American National Standard for Use of
consideration.
theInternationalSystemofUnits(SI):TheModernMetric
1.2 The purpose of this specification is to document the
System
4
minimum acceptable properties and levels of quality assurance
2.2 ASME Standards:
and traceability for nuclear grade graphite suitable for compo-
NQA-1 Quality Assurance Program Requirements for
nents subjected to low irradiation dose. Nuclear graphites
Nuclear Facilities
meeting the requirements of Specification D7219 are also
suitable for components subjected to low neutron irradiation 3. Terminology
dose.
3.1 Definitions—Definitionsrelatingtothisspecificationare
1.3 The values stated in SI units are to be regarded as given in Terminology C709. See Table 1.
standard. No other units of measurement are included in this
3.2 Definitions of Terms Specific to This Standard:
standard.
3.2.1 anistropic nuclear graphite, n—graphite in which the
isotropy ratio based on the coefficient of thermal expansion is
2. Referenced Documents
greater than 1.15.
2
2.1 ASTM Standards:
3.2.2 baking/re-baking charge, n—number of billets in a
C559Test Method for Bulk Density by Physical Measure-
baking/re-baking furnace run.
ments of Manufactured Carbon and Graphite Articles
3.2.3 bulk density, n—mass of a unit volume of material
C709Terminology Relating to Manufactured Carbon and
3 including both permeable and impermeable voids.
Graphite (Withdrawn 2017)
3.2.4 extrusion forming lot, n—number of billets of the
C781PracticeforTestingGraphiteMaterialsforGas-Cooled
same size extruded in an uninterrupted sequence.
Nuclear Reactor Components
C838Test Method for Bulk Density of As-Manufactured
3.2.5 green batch, n—mass of coke, recycle green mix,
Carbon and Graphite Shapes
recycle graphite, and pitch that is required to produce a
forming lot.
3.2.6 green mix, n—percentage of mix formulation, pitch
1
This specification is under the jurisdiction of ASTM Committee D02 on
and additives required for the forming lot, which is processed
Petroleum Products, Liquid Fuels, and Lubricants and is the direct responsibility of
and ready to be formed.
Subcommittee D02.F0 on Manufactured Carbon and Graphite Products.
CurrenteditionapprovedJune1,2015.PublishedJuly2015.Originallyapproved
3.2.7 graphite billet, n—extruded, molded, or iso-molded
in 2008. Last previous edition approved in 2011 as D7301–11. DOI: 10.1520/
graphite artifact with dimensions sufficient to meet the design-
D7301-11R15.
2
For referenced ASTM standards, visit the ASTM website, www.astm.org, or er’s requirements for reactor components.
contact ASTM Customer Service at [e-mail]. For Annual Book of ASTM
Standards volume information, refer to the standard’s Document Summary page on
4
the ASTM website. Available from American Society of Mechanical Engineers (ASME), ASME
3
The last approved version of this historical standard is referenced on International Headquarters, Three Park Ave., New York, NY 10016-5990, http://
www.astm.org. www.asme.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
D7301−11 (2015)
TABLE 1 ASTM Graphite Grain Size Definitions from Terminology
3.2.19 purification charge, n—number of billets in a purifi-
C709
cation run.
Graphite Definition of Grains in
3.2.20 recycle green mix, n—ground non-baked billets or
A
Designation the Starting Mix that are:
B
Medium Grained Generally<4mm non-used green mix manufactured in compliance with the mix
Fine Grained Generally
...

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 D7301 − 11 (Reapproved 2015) An American National Standard
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
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.
2. Referenced Documents
2
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
C781 Practice for Testing Graphite and Boronated Graphite Materials for High-Temperature 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
D7219 Specification for Isotropic and Near-isotropic Nuclear Graphites
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 C709. 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.
1
This specification is under the jurisdiction of ASTM Committee D02 on Petroleum Products Products, Liquid Fuels, and Lubricants and is the direct responsibility of
Subcommittee D02.F0 on Manufactured Carbon and Graphite Products.
Current edition approved Oct. 1, 2011June 1, 2015. Published November 2011July 2015. Originally approved in 2008. Last previous edition approved in 20082011 as
D7301D7301 – 11.–08. DOI: 10.1520/D7301-11.10.1520/D7301-11R15.
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.
3
Available from American Society of Mechanical Engineers (ASME), ASME International Headquarters, Three Park Ave., New York, NY 10016-5990, http://
www.asme.org.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
D7301 − 11 (2015)
TABLE 1 ASTM Graphite Grain Size Definitions from Terminology
C709
Graphite Definition of Grains in
A
Designation the Starting Mix that are:
B
Medium Grained Generally < 4 mm
Fine Grained Generally < 100 μm
Superfine Grained Generally < 50 μm
Ultrafine Grained Generally < 10 μm
Microfine Grained Generally < 2 μm
A
Grain size as defined in Terminology C709.
B
For Nuclear graphite, the maximum grain size is 1.68 mm 1.68 mm in accor-
dance with 4.2.1.6.
3.2.5 gre
...