ASTM C625-15(2021)

Standard Practice for Reporting Irradiation Results on Graphite

SIGNIFICANCE AND USE
4.1 The purpose of this practice is to identify sample and test parameters that may influence graphite irradiation test results. This practice should not be construed as a requirement or recommendation that proprietary information be disclosed.  
4.2 Irradiation results on graphite include dimensional changes and changes in properties that are used in reactor design. The irradiation data are reported in government documents, open literature publications, and are assembled into data manuals for use by reactor designers.
SCOPE
1.1 This practice covers information recommended for inclusion in reports giving graphite irradiation results.  
1.2 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-Mar-2021
• ICS: 71.060.10 - Chemical elements
• Technical Committee: D02 - Petroleum Products, Liquid Fuels, and Lubricants
• Drafting Committee: D02.F0 - Manufactured Carbon and Graphite Products

Relations

• Refers: ASTM E261-15 - Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
• Effective Date: 01-Jun-2015
• Refers: ASTM E261-10 - Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
• Effective Date: 01-Jan-2010
• Refers: ASTM E261-03 - Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
• Effective Date: 10-Jul-2003
• Refers: ASTM E261-98 - Standard Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
• Effective Date: 10-Jan-1998
• Refers: ASTM E525-90(1996) - Practice for Reporting Dosimetry Results on Nuclear Graphite (Withdrawn 2001)
• Effective Date: 01-Jan-1996

Overview

ASTM C625-15(2021), Standard Practice for Reporting Irradiation Results on Graphite, establishes comprehensive guidelines for documenting and reporting the results of irradiation tests performed on graphite materials. Developed by ASTM, this international standard ensures consistency and completeness in reporting data that is critical to the design and analysis of nuclear reactors and other applications utilizing irradiated graphite. ASTM C625 outlines the required details concerning samples, test parameters, irradiation conditions, and measurement techniques to support thorough evaluation and reproducibility of results.

Key Topics

• Sample Description: The standard specifies requirements for reporting the source, grade (or identifying number), raw materials (including filler, binder, additives, and impregnants), forming processes, heat treatment, purification steps, sampling plans, and pre-irradiation treatments.
• Property Measurements: Emphasis is placed on disclosing the methods and accuracy of both pre- and post-irradiation measurements, referencing applicable standards and indicating the number of samples involved.
• Irradiation Conditions: Detailed recording is required on the reactor and test positions, capsule design, atmospheric exposure, thermal history, dosimetry methods (including neutron fluence), and any applied stress or constraints during irradiation.
• Reporting Guidelines: The standard sets forth a framework for assembling comprehensive irradiation test reports while explicitly noting that proprietary information need not be disclosed.
• Applicability: ASTM C625 underlines its role in supporting reactor designers by contributing to data manuals and literature used in evaluating the performance of graphite under irradiation.

Applications

ASTM C625 is particularly valuable for professionals and organizations in the nuclear energy sector, research facilities, and graphite manufacturing. Adhering to this practice aids in:

• Reactor Design: Ensuring that irradiation data on graphite is reported consistently and accurately is essential for reactor designers evaluating material behavior under radiation.
• Data Comparison and Analysis: Uniform reporting facilitates comparison of irradiation results across different studies, enabling more reliable interpretation of dimensional stability, mechanical strength, and property changes in graphite.
• Regulatory Compliance: The standard supports compliance with international requirements for material reporting, as shaped by the World Trade Organization Technical Barriers to Trade (TBT) Committee principles.
• Quality Assurance: Manufacturers and laboratories benefit from improved quality control and traceability in graphite testing and reporting processes.

Related Standards

For comprehensive reporting and analysis, ASTM C625 references and aligns with these key standards:

• ASTM E261: Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques - used for dosimetry in irradiation testing.
• ASTM E525: Practice for Reporting Dosimetry Results on Nuclear Graphite (withdrawn) - previously referenced for dosimetry reporting.
• International Standards Principles: Developed in line with WTO TBT Committee guidelines on standardization.

Key terms: graphite, irradiation results, reporting, ASTM C625, nuclear reactor materials, property changes, dosimetry, sample parameters, international standards.

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: C625 − 15 (Reapproved 2021)
Standard Practice for
Reporting Irradiation Results on Graphite
This standard is issued under the fixed designation C625; 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 documents,openliteraturepublications,andareassembledinto
data manuals for use by reactor designers.
1.1 This practice covers information recommended for in-
clusion in reports giving graphite irradiation results.
5. Sample Description
1.2 This international standard was developed in accor-
5.1 Source,
dance with internationally recognized principles on standard-
5.2 Grade or identifying sample number,
ization established in the Decision on Principles for the
Development of International Standards, Guides and Recom-
5.3 Rawmaterialsincludingfiller,binder,additives,impreg-
mendations issued by the World Trade Organization Technical
nants and their pretreatment, if not proprietary information,
Barriers to Trade (TBT) Committee.
5.4 Forming process including the size and shape of parent
stock, if not proprietary information,
2. Referenced Documents
2 5.5 Heat treatment including graphitizing temperature, rate
2.1 ASTM Standards:
of heating and soak time, if not proprietary information.
E261 Practice for Determining Neutron Fluence, Fluence
Rate, and Spectra by Radioactivation Techniques 5.6 Purification, if not proprietary information,
E525 Practice for Reporting Dosimetry Results on Nuclear
5.7 Sampling plan including location in parent stock, grain
Graphite (Withdrawn 2001)
orientation, size, and shape of samples, and
5.8 Pre-irradiation sample treatment including prestressing,
3. Terminology
annealing, or previous irradiation.
3.1 Definitions:
3.1.1 grade, n—designation given a material by a manufac-
6. Property Measurements
turer such that it is always reproduced to the same specifica-
6.1 Method—Indicate the method and accuracy of measure-
tions established by the manufacturer.
ment and, if applicable, differences between pre- and post-
irradiation measurements. Where applicable, give reference to
4. Significance and Use
standards or guides that prescribe (or describe) the method
4.1 The purpose of this practice is to identify sample and
used.
test parameters that may influence graphite irradiation test
6.2 Results—Specify the number of samples represented or
results. This practice should not be construed as a requirement
the number of measurements per sample if mean values are
or recommendation that proprietary information be disclosed.
given.
4.2 Irradiation results on graphite include dimensional
6.3 Indicate other measurements taken but not reported.
changes and changes in properties that are used in r
...