Equibiaxial Flexure Strength of a Superfine-Grained Nuclear Graphite
Author:
Affiliation:
1. Oak Ridge National Laboratory, Materials Science and Technology Division, P.O. Box 2008, Oak Ridge, TN 37831, US
Publisher
ASTM International
Reference10 articles.
1. American Society of Mechanical Engineers, “High Temperature Reactors,” in ASME Boiler and Pressure Vessel Code: An International Code, (New York: Author, 2019), 380–434.
2. Standard Test Method for Monotonic Equibiaxial Flexural Strength of Advanced Ceramics at Ambient Temperature, ASTM C1499-05 (West Conshohocken, PA: ASTM International, approved June 1, 2005), https://doi.org/10.1520/C1499-05
3. The Development of a Stress Analysis Code for Nuclear Graphite Components in Gas-Cooled Reactors;Tsang;Journal of Nuclear Materials,2006
4. Standard Terminology Relating to Manufactured Carbon and Graphite, ASTM C709-09 (West Conshohocken, PA: ASTM International, approved December 1, 2009), https://doi.org/10.1520/C0709-09
5. Standard Specification for Isotropic and Near-Isotropic Nuclear Graphites, ASTM D7219-19 (West Conshohocken, PA: ASTM International, approved November 1, 2019), https://doi.org/10.1520/D7219-19
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