ASTM-C781 › Standard Practice for Testing Graphite Materials for Gas-Cooled Nuclear Reactor Components
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Scope
1.1 This practice covers the test methods for measuring those properties of graphite and boronated graphite materials that may be used for the design and evaluation of high-temperature gas-cooled reactors.
1.2 The test methods referenced herein are applicable to materials used for replaceable and permanent components as defined in Section 7 and include fuel and removable reflector elements; target elements and insulators; permanent side reflector elements; 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 for boronated graphite components are given in Sections 8 and 10, respectively. The test methods are summarized in Tables 1 and 2.
1.4 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.
Keywords
boronated graphite; chemical properties; graphite; high temperature gas-cooled nuclear reactor; mechanical properties; neutronic properties; physical properties; thermal properties; ICS Number Code 27.120.10 (Reactor engineering)
To find similar documents by ASTM Volume:
05.05 (Combustion Characteristics; Manufactured Carbon and Graphite Products; Catalysts)
To find similar documents by classification:
27.120.10 (Reactor engineering)
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Document Number
ASTM-C0781-20
Revision Level
2020 EDITION
Status
Current
Modification Type
Revision
Publication Date
June 17, 2020
Document Type
Practice
Page Count
10 pages
Committee Number
D02.F0