Effects of burn-off on strengths and toughnesses of carbon materials
- 1. Ibaraki Univ., Hitachi (Japan). Faculty of Engineering
Description
The purpose of this study is to evaluate the effects of burn-off at 500degC by air oxidation on strengths and fracture toughnesses of a carbon-fiber-reinforced carbon composite and three fine-grained isotropic graphite materials that are used as main materials of plasma facing components for fusion reactor devices and core structural materials of gas-cooled nuclear reactors. The Young's moduli, the bending strengths, the Rockwell hardnesses, the mode I fracture toughnesses and the load and depth by a manufactured hardness tester were measured and the microstructures of the fracture surfaces were examined. The degradations due to burn-off of these properties of CX-2002 U composite were the smallest and those of IG-430 U graphite were less marked than those of other graphite materials. After oxidation of the C/C composite, preferential removal of the boundary layer between carbon fiber and pyrolytic carbon matrix and carbon fiber were observed. After oxidation of graphite materials, the size and the number of pores were increased and the fracture surfaces were rough due to oxidation of graphite grain boundaries. (author)
Additional details
Publishing Information
- Journal Title
- Nippon Kikai Gakkai Ronbunshu, A Hen
- Journal Volume
- 63
- Journal Issue
- 608
- Journal Page Range
- p. 838-844.
- ISSN
- 0387-5008
- CODEN
- NKGADA
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 28054811
- Subject category
- S36: MATERIALS SCIENCE;
- Descriptors DEI
- CARBON FIBERS; COMPOSITE MATERIALS; FIRST WALL; FRACTURE PROPERTIES; GRAPHITE; HTGR TYPE REACTORS; MICROSTRUCTURE; OXIDATION; PLASMA; REACTOR CORES; REACTOR MATERIALS; ROCKWELL HARDNESS; SCANNING ELECTRON MICROSCOPY; THERMONUCLEAR REACTOR MATERIALS; YOUNG MODULUS
- Descriptors DEC
- CARBON; CHEMICAL REACTIONS; CRYSTAL STRUCTURE; ELECTRON MICROSCOPY; ELEMENTS; FIBERS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MATERIALS; MECHANICAL PROPERTIES; MICROSCOPY; NONMETALS; REACTOR COMPONENTS; REACTORS; THERMONUCLEAR REACTOR WALLS