Mechanical Properties of Cubic Silicon Carbide after Neutron Irradiation at Elevated Temperatures

Volume 2, Issue 8 (September 2005)

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ISSN: 1546-962X
CODEN: JAIOAD
Published Online: 22 June 2005
Page Count: 13

Mechanical Properties of Cubic Silicon Carbide after Neutron Irradiation at Elevated Temperatures

Katoh, Y
Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge, TN

Snead, LL
Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge, TN

(Received 16 April 2004; accepted 30 January 2005)

Abstract

Mechanical properties of high-purity polycrystalline cubic SiC was characterized after neutron irradiation. Bar samples were irradiated in target position capsules in the High Flux Isotope Reactor (HFIR, Oak Ridge, Tennessee) to nominal fluence levels up to 7.7 dpa at temperatures of 300, 500, and 800°C. A decrease in Young's modulus was observed after irradiation, and its irradiation temperature dependence qualitatively agreed with the calculated modulus change due to point defect swelling. Irradiation caused a significant modification of statistical flexural strength but caused only minor increase in nano-indentation hardness. The irradiation effect on fracture initiation through an enhanced cleavage resistance likely is primarily responsible for the major change in flexural strength properties.

Keywords:
silicon carbide, neutron irradiation, nano-indentation, elastic modulus, flexural strength

Paper ID: JAI12377
DOI: 10.1520/JAI12377
ASTM International is a member of CrossRef.

Author Title Mechanical Properties of Cubic Silicon Carbide after Neutron Irradiation at Elevated Temperatures Symposium Effects of Radiation on Materials: 22nd International Symposium, 2004-06-10 Committee E10

		SEDL / Journals / Journal of ASTM International (JAI) / Citation Page Volume 2, Issue 8 (September 2005) Click here to download this paper now for $25 PDF (1.1M) View License Agreement ISSN: 1546-962X CODEN: JAIOAD Published Online: 22 June 2005 Page Count: 13 Mechanical Properties of Cubic Silicon Carbide after Neutron Irradiation at Elevated Temperatures Katoh, Y Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge, TN Snead, LL Metals and Ceramics Division, Oak Ridge National Laboratory, Oak Ridge, TN (Received 16 April 2004; accepted 30 January 2005) Abstract Mechanical properties of high-purity polycrystalline cubic SiC was characterized after neutron irradiation. Bar samples were irradiated in target position capsules in the High Flux Isotope Reactor (HFIR, Oak Ridge, Tennessee) to nominal fluence levels up to 7.7 dpa at temperatures of 300, 500, and 800°C. A decrease in Young's modulus was observed after irradiation, and its irradiation temperature dependence qualitatively agreed with the calculated modulus change due to point defect swelling. Irradiation caused a significant modification of statistical flexural strength but caused only minor increase in nano-indentation hardness. The irradiation effect on fracture initiation through an enhanced cleavage resistance likely is primarily responsible for the major change in flexural strength properties. Keywords: silicon carbide, neutron irradiation, nano-indentation, elastic modulus, flexural strength Paper ID: JAI12377 DOI: 10.1520/JAI12377 ASTM International is a member of CrossRef. Author Title Mechanical Properties of Cubic Silicon Carbide after Neutron Irradiation at Elevated Temperatures Symposium Effects of Radiation on Materials: 22nd International Symposium, 2004-06-10 Committee E10