ASTM C781

Property data obtained with the recommended test methods identified herein may be used for research and development, design, manufacturing control, specifications, performance evaluation, and regulatory statutes pertaining to high temperature gas-cooled reactors.

The test methods are applicable primarily to specimens in the non-irradiated and non-oxidized state. Many are also applicable to specimens in the irradiated or oxidized state, or both, provided the specimens meet all requirements of the test method. The user is cautioned to consider the instructions given in the test methods.

Additional test methods are in preparation and will be incorporated. The user is cautioned to employ the latest revision.

1. Scope

1.1 This practice covers the test methods for measuring the properties of graphite and boronated graphite materials. These properties may be used for the design and evaluation of high-temperature gas-cooled reactor components.

1.2 The test methods referenced herein are applicable to materials used for replaceable and permanent components as defined in Section 7 and Section 9, and includes fuel elements; removable reflector elements and blocks; permanent side reflector elements and blocks; core support pedestals and elements; control rod, reserve shutdown, and burnable poison compacts; and neutron shield material.

1.3 This practice includes test methods that have been selected from existing ASTM standards, ASTM standards that have been modified, and new ASTM standards that are specific to the testing of materials listed in 1.2. Comments on individual test methods for graphite and boronated graphite components are given in Sections 8 and 10, respectively. The test methods are summarized in Tables 1 and 2.

1.4 The values stated in SI units are to be regarded as standard. The values given in parentheses are for information only.

1.5 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 and health practices and determine the applicability of regulatory limitations prior to use.

2. Referenced Documents

C1179 Test Method for Oxidative Mass Loss of Manufactured Carbon and Graphite Materials in Air
C1251 Test Method for Determination of Specific Surface Areas of Advanced Ceramic Materials by Gas Adsorption
C559 Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles
C560 Test Methods for Chemical Analysis of Graphite
C561 Test Method for Ash in a Graphite Sample
C577 Test Method for Permeability of Refractories
C625 Practice for Reporting Irradiation Results on Graphite
C626 Methods for Estimating the Thermal Neutron Absorption Cross Section of Nuclear Graphite
C651 Test Method for Flexural Strength of Manufactured Carbon and Graphite Articles Using Four-Point Loading at Room Temperature
C695 Test Method for Compressive Strength of Carbon and Graphite
C709 Terminology Relating to Manufactured Carbon and Graphite
C747 Test Method for Moduli of Elasticity and Fundamental Frequencies of Carbon and Graphite Materials by Sonic Resonance
C749 Test Method for Tensile Stress-Strain of Carbon and Graphite
C816 Test Method for Sulfur in Graphite by Combustion-Iodometric Titration Method
C838 Test Method for Bulk Density of As-Manufactured Carbon and Graphite Shapes
D2854 Test Method for Apparent Density of Activated Carbon
D2862 Test Method for Particle Size Distribution of Granular Activated Carbon
D4292 Test Method for Vibrated Bulk Density of Calcined Petroleum Coke
E132 Test Method for Poisson's Ratio at Room Temperature
E1461 Test Method for Thermal Diffusivity of Solids by the Flash Method
E228 Test Method for Linear Thermal Expansion of Solid Materials with a Vitreous Silica Dilatometer
E261 Practice for Determining Neutron Fluence Rate, Fluence, and Spectra by Radioactivation Techniques

Index Terms

boronated graphite; chemical properties; graphite; high temperature gas-cooled nuclear reactor; mechanical properties; neutronic properties; physical properties; thermal properties; Boronated graphite; Carbon; Chemical analysis--nuclear materials; Core support blocks/posts/seats; Design--nuclear materials/applications; Graphite; High-temperature gas-cooled nuclear reactor; Neutronic properties; Nuclear graphite; Property data; Research and development applications; Thermal conductance/conductivity; ICS Number Code 27.120.10

Citing ASTM Standards

[Back to Top]