ASTM C 781 Standard Practice for Testing Graphite and Boronated Graphite Materials for High-Temperature Gas-Cooled Nuclear Reactor Components
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ASTM C 781 Document Information:
Title
Standard Practice for Testing Graphite and Boronated Graphite Materials for High-Temperature Gas-Cooled Nuclear Reactor Components
ASTM International
Publication Date:
Sep 1, 2008
Scope:
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.
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.
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.
The values stated in SI units are to be regarded as standard.
The values given in parentheses are for information only.
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.
*A Summary of Changes section appears at the end of this
standard.
Keywords:
- boronated graphite
- chemical properties
- graphite
- high temperature gas-cooled nuclear reactor
- mechanical properties
- neutronic properties
- physical properties
- thermal properties
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