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Title: Tensile Properties of Advanced SiC/SiC Composites for Nuclear Control Rod Applications

Abstract

No abstract prepared.

Authors:
 [1];  [1];  [1];  [2]
  1. ORNL
  2. Hyper-Therm High-Temperature Composites, Inc.
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); High Temperature Materials Laboratory
Sponsoring Org.:
Work for Others (WFO)
OSTI Identifier:
978739
DOE Contract Number:
DE-AC05-00OR22725
Resource Type:
Conference
Resource Relation:
Conference: 31st International Conference & Exposition on Advanced Ceramics & Composites, Daytona Beach, FL, USA, 20070121, 20070126
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; CERAMICS; CONTROL ELEMENTS; TENSILE PROPERTIES

Citation Formats

Nozawa, Takashi, Lara-Curzio, Edgar, Katoh, Yutai, and Shinavski, Robert J. Tensile Properties of Advanced SiC/SiC Composites for Nuclear Control Rod Applications. United States: N. p., 2007. Web.
Nozawa, Takashi, Lara-Curzio, Edgar, Katoh, Yutai, & Shinavski, Robert J. Tensile Properties of Advanced SiC/SiC Composites for Nuclear Control Rod Applications. United States.
Nozawa, Takashi, Lara-Curzio, Edgar, Katoh, Yutai, and Shinavski, Robert J. Mon . "Tensile Properties of Advanced SiC/SiC Composites for Nuclear Control Rod Applications". United States. doi:.
@article{osti_978739,
title = {Tensile Properties of Advanced SiC/SiC Composites for Nuclear Control Rod Applications},
author = {Nozawa, Takashi and Lara-Curzio, Edgar and Katoh, Yutai and Shinavski, Robert J},
abstractNote = {No abstract prepared.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Jan 01 00:00:00 EST 2007},
month = {Mon Jan 01 00:00:00 EST 2007}
}

Conference:
Other availability
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  • Composite materials have the potential for their properties to be tailored to specific applications by engineering the combination of fibers and matrices. Ceramic matrix composites are attractive because of their excellent high-temperature properties and corrosion resistance. In particular, ceramic composites made from silicon carbide fibers and silicon carbide matrices (SiCf/SiC) are promising for nuclear applications because of the radiation resistance of the β-phase of SiC, their excellent high-temperature fracture, creep, corrosion and thermal shock resistance. The β-phase of SiC has been shown by numerous studies to have a saturation swelling value of about 0.1 to 0.2% at 800 to 1000°C.more » This suggests that composites of SiC/SiC have the potential for excellent radiation stability. The continuous fiber architecture, coupled with engineered interfaces between the fiber and matrix, provide excellent fracture properties and fracture toughness values on the order of 25 MPa m1/2. The strength and fracture toughness are independent of temperature up to the limit of the fiber stability. Also, these fiber/matrix microstructures impart excellent thermal shock and thermal fatigue resistance so start-up and shut-down cycles and coolant loss scenarios should not induce significant structural damage.« less
  • CVD of carbon (derived from two different precursors) on SiC and B4C matrices has been employed to yield single-strand unidirectional composites. The tensile strength of carbon deposited via pyrolysis of propylene was higher than that of methane pyrolysis-deposited carbon matrices. A novel CVD boron-carbon interface has also been developed which does not degrade carbon yarns and yields composites exhibiting high strengths; these strength levels were, moreover, highly resistant to long-duration, high-temperature annealing. Coated fibers and composites have been characterized by SEM and XRD. 8 refs.