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ASTM C625-15

(Practice)

Standard Practice for Reporting Irradiation Results on Graphite

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.

General Information

Status
Historical
Publication Date
30-Sep-2015
ICS
71.060.10 - Chemical elements
Technical Committee
D02 - Petroleum Products, Liquid Fuels, and Lubricants
Drafting Committee
D02.F0 - Manufactured Carbon and Graphite Products
Current Stage
Ref Project

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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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.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: C625 − 15
Standard Practice for
1
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* 5.3 Rawmaterialsincludingfiller,binder,additives,impreg-
nants and their pretreatment, if not proprietary information,
1.1 This practice covers information recommended for in-
clusion in reports giving graphite irradiation results. 5.4 Forming process including the size and shape of parent
stock, if not proprietary information,
2. Referenced Documents
5.5 Heat treatment including graphitizing temperature, rate
2
2.1 ASTM Standards:
of heating and soak time, if not proprietary information.
E261 Practice for Determining Neutron Fluence, Fluence
5.6 Purification, if not proprietary information,
Rate, and Spectra by Radioactivation Techniques
E525 Practice for Reporting Dosimetry Results on Nuclear 5.7 Sampling plan including location in parent stock, grain
3
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 reactor
design. The irradiation data are reported in government
7. Irradiation Conditions
documents,openliteraturepublications,andareassembledinto
data manuals for use by reactor designers.
7.1 Reactor and test positions.
7.2 Design of capsule, including materials of construction.
5. Sample Description
7.3 Atmosphere to which samples were exposed.
5.1 Source,
7.4 Thermal history including method of measurement or
5.2 Grade or identifying sample number,
calculation.
7.5 Sample Constraint—If applicable, indicate the type,
1
This practice is under the jurisdiction of ASTM Committee D02 on Petro
...

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: C625 − 95 (Reapproved 2010) C625 − 15 An American National Standard
Standard Practice for
1
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 Scope*
1.1 This practice covers information recommended for inclusion in reports giving graphite irradiation results.
2. Referenced Documents
2
2.1 ASTM Standards:
E261 Practice for Determining Neutron Fluence, Fluence Rate, and Spectra by Radioactivation Techniques
3
E525 Practice for Reporting Dosimetry Results on Nuclear Graphite (Discontinued 2001) (Withdrawn 2001)
3. Terminology
3.1 Definitions:
3.1.1 grade, n—designation given a material by a manufacturer such that it is always reproduced to the same specifications
established by the manufacturer.
4. 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.
5. Sample Description
5.1 Source,
5.2 Grade or identifying sample number,
5.3 Raw materials including filler, binder, additives, impregnants and their pretreatment, if not proprietary information,
5.4 Forming process including the size and shape of parent stock, if not proprietary information,
5.5 Heat treatment including graphitizing temperature, rate of heating and soak time, if not proprietary information.
5.6 Purification, if not proprietary information,
5.7 Sampling plan including location in parent stock, grain orientation, size, and shape of samples, and
5.8 Pre-irradiation sample treatment including prestressing, annealing, or previous irradiation.
6. Property Measurements
6.1 Method—Indicate the method and accuracy of measurement and, if applicable, differences between pre- and post-irradiation
measurements. Where applicable, give reference to standards or guides that prescribe (or describe) the method used.
6.2 Results—Specify the number of samples represented or the number of measurements per sample if mean values are given.
1
This practice 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 May 1, 2010Oct. 1, 2015.
...

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5.1 Two- and three-parameter formulations exist for the Weibull distribution. This practice is restricted to the two-parameter formulation. An objective of this practice is to obtain point estimates of the unknown Weibull distribution parameters by using well-defined functions that incorporate the failure data. These functions are referred to as estimators. It is desirable that an estimator be consistent and efficient. In addition, the estimator should produce unique, unbiased estimates of the distribution parameters (6). Different types of estimators exist, such as moment estimators, least-squares estimators, and maximum likelihood estimators. This practice details the use of maximum likelihood estimators.  
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3.1 This test method is primarily concerned with the oxidation mass loss of manufactured carbon and graphite materials in air at temperatures from 371 °C to 677 °C.  
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5.1 The molten salt reactor is a nuclear reactor which uses graphite as reflector and structural material and fluoride molten salt as coolant. The graphite components will be submerged in the molten salt during the lifetime of the reactor. The porous structure of graphite may lead to molten salt permeation, which can affect the thermal and mechanical properties of graphite. Consequently, it is important to assess the effect of impregnation of molten salt on the properties of the as-manufactured graphite material.  
5.2 The purpose of this guide is to report considerations that should be included in the preparation of graphite specimens representative of that after exposure to a molten salt environment. The degree to which the molten salt will infiltrate the graphite will depend upon a number of factors, including the type of graphite and the type and extent of porosity, the properties of the molten salt, the impregnation pressure and temperature, and the duration of the exposure of the graphite to the molten salt.  
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5.5.1 The density of molten salt is greater than that of graphite. A specially designed tool is required to submerge graphite samples in the molten salt during the impregnation process.  
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1.1 This guide covers procedures for the impregnation of graphite with molten salt under a consistent pressure and temperature. Such procedures are necessary if the user wishes to prepare graphite specimens for testing that represent material that has been exposed to a molten salt environment in a molten salt nuclear reactor. The user will need to ensure that impregnation temperature and pressure conditions reflect those pertaining to the molten salt environment, noting that the properties of the material will change once it becomes irradiated.
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1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this guide.  
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ASTM D8377-21a(Guide)
Standard Guide for High Temperature Strength Measurements of Graphite Impregnated with Molten Salt

SIGNIFICANCE AND USE
5.1 The Molten Salt Reactor is a nuclear reactor which uses graphite as reflector and structural material, and molten salt as coolant. The graphite components will be submerged in the molten salt during the lifetime of the reactor. The porous structure of graphite may lead to molten salt permeation, which can affect the thermal and mechanical properties of graphite. Consequently, it may be necessary to measure the various strengths of the manufactured graphite materials after impregnation with molten salt and before exposure to the reactor environment in a range of test configurations in order for designers or operators to assess their performance.
Note 1: Depending upon the salt selected for the reactor, there may be some chemical reaction between the salt and the graphite that could affect properties. The user should establish, prior to following this guide, that any interactions between the molten salt and graphite are understood and any implications for the validity of the strength tests have been assessed.  
5.2 For gas-cooled reactors, the strength of a graphite specimen is usually measured at room temperature. However, for molten salt reactors, the operating temperature of the reactor must be higher than the melting temperature of the salt, and so the salt will be in solid state at room temperature. Consequently, room temperature measurements may not be representative of the performance of the material at its true operating conditions. It is therefore necessary to measure the strength at an elevated temperature where the salt is in liquid form.
Note 2: Users should be aware that a small increase in graphite strength is expected with increasing temperature. Testing at the plant operating temperature will eliminate this small uncertainty.  
5.3 The purpose of this guide is to provide considerations, which should be included in testing graphite specimens impregnated with molten salt at elevated temperature.  
5.4 For the test results to be meaningful, the...
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1.1 This guide covers the best practice for strength measurements at elevated temperature of graphite impregnated with molten salt.  
1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
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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.

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ASTM C695-21(Test Method)
Standard Test Method for Compressive Strength of Carbon and Graphite

SIGNIFICANCE AND USE
4.1 Carbon and graphite can usually support higher loads in compression than in any other mode of stress. This test, therefore, provides a measure of the maximum load-bearing capability of carbon and graphite objects.
SCOPE
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1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.  
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.

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