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ASTM C625-95(2010)

(Practice)

Standard Practice for Reporting Irradiation Results on Graphite

Standard Practice for Reporting Irradiation Results on Graphite

SIGNIFICANCE AND USE
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.
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-Apr-2010
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

Relations

Replaces
ASTM C625-95(2005) - Standard Practice for Reporting Irradiation Results on Graphite
Effective Date
01-May-2010
Referred By
ASTM C781-20 - Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components
Effective Date
01-May-2010
Referred By
ASTM C1783-15 - Standard Guide for Development of Specifications for Fiber Reinforced Carbon-Carbon Composite Structures for Nuclear Applications
Effective Date
01-May-2010
Referred By
ASTM C1793-15 - Standard Guide for Development of Specifications for Fiber Reinforced Silicon Carbide-Silicon Carbide Composite Structures for Nuclear Applications
Effective Date
01-May-2010

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ASTM C625-95(2010) - Standard Practice for Reporting Irradiation Results on GraphiteASTM C625-95(2010) - Standard Practice for Reporting Irradiation Results on Graphite
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ASTM C625-95(2010) - Standard Practice for Reporting Irradiation Results on Graphite
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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.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 − 95(Reapproved 2010) An American National Standard
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 4.4 Forming process including the size and shape of parent
stock, if not proprietary information,
1.1 This practice covers information recommended for in-
clusion in reports giving graphite irradiation results. 4.5 Heat treatment including graphitizing temperature, rate
of heating and soak time, if not proprietary information.
2. Referenced Documents
4.6 Purification, if not proprietary information,
2.1 ASTM Standards:
4.7 Sampling plan including location in parent stock, grain
E261 Practice for Determining Neutron Fluence, Fluence
orientation, size, and shape of samples, and
Rate, and Spectra by Radioactivation Techniques
E525 Practice for Reporting Dosimetry Results on Nuclear
4.8 Pre-irradiation sample treatment including prestressing,
Graphite (Discontinued 2001) (Withdrawn 2001) annealing, or previous irradiation.
3. Significance and Use
5. Property Measurements
3.1 The purpose of this practice is to identify sample and
5.1 Method—Indicate the method and accuracy of measure-
test parameters that may influence graphite irradiation test
ment and, if applicable, differences between pre- and post-
results. This practice should not be construed as a requirement
irradiation measurements.
or recommendation that proprietary information be disclosed.
5.2 Results—Specify the number of samples represented or
3.2 Irradiation results on graphite include dimensional
the number of measurements per sample if mean values are
changes and changes in properties that are used in reactor
given.
design. The irradiation data are reported in government
5.3 Indicate other measurements taken but not reported.
documents,openliteraturepublications,andareassembledinto
data manuals for use by reactor designers.
6. Irradiation Conditions
4. Sample Description
6.1 Reactor and test positions.
4.1 Source,
6.2 Design of capsule, including materials of construction.
4.2 Grade or identifying sample number,
6.3 Atmosphere to which samples were exposed.
4.3 Rawmaterialsincludingfiller,binder,additives,impreg-
6.4 Thermal history including method of measurement or
nants and their pretreatment, if not proprietary information,
calculation.
6.5 Sample Constraint—If applicable, indicate the type,
This practi
...

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ASTM C561-23(Test Method)
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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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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.  
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ASTM D8091-21(Guide)
Standard Guide for Impregnation of Graphite 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 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.  
5.3 The user of this guide will need to select impregnation parameters sufficiently representative of those in a molten salt reactor based on parameters provided by the designer. Alternatively, the user may select a standard set of impregnation conditions to allow comparisons across a range of graphites.  
5.4 This guide is not intended to be prescriptive. A typical apparatus and associated procedure are described. Some indication of the sensitivity of the procedure to graphite type and impregnation conditions is given in He, et al.5  
5.5 There are four major practical issues that must be addressed during the impregnation process:  
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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Standard Test Method for Compressive Strength of Carbon and Graphite

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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.
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