Open AccessTest Methods for Hoop Tensile Strength of Ceramic Composite Tubes for Light Water Nuclear Reactor Applications
Author(s) -
Michael G. Jenkins,
Jonathan A. Salem
Publication year - 2013
Publication title -
ceramic engineering and science proceedings
Language(s) - English
Resource type - Book series
SCImago Journal Rank - 0.128
H-Index - 33
eISSN - 1940-6339
pISSN - 0196-6219
DOI - 10.1002/9781118807934.ch12
Subject(s) - ultimate tensile strength , composite number , tensile testing , materials science , test (biology) , scope (computer science) , structural engineering , nuclear engineering , ceramic , composite material , engineering , computer science , geology , paleontology , programming language
SiC/SiC CMC materials and structure technology was funded by the aerospace and defense industries/agencies. Current evaluations and applications of SiC/SiC CMCs in fusion reactors (first wall) and TRISO fuel forms that have established properties under extended neutron irradiation and at high temperatures as well as very hot steam environment. Growing, credible data bases for SiC/SiC CMCs now exist because of the evolution of consensus test methods and design codes. Maturation of volume-scale manufacturing capability for all types of CMCs including SiC/SiC CMC adds to availability and understanding of these material.
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