Oxidation behavior and property change of nuclear grade C/C composite

原子炉級C/C複合材料の酸化挙動及び特性評価

Kim, W. J.*; Seo, M.-R.*; Park, J. Y.*; 角田 淳弥 ; 柴田 大受 ; 沢 和弘

Kim, W. J.*; Seo, M.-R.*; Park, J. Y.*; Sumita, Junya; Shibata, Taiju; Sawa, Kazuhiro

C/C複合材料は、優れた機械的特性及び耐熱衝撃性を有することから、高温構造材として使用されている。原子力分野では、核融合炉のプラズマ対向壁及びガス冷却炉の高温構造材の候補となっている。高温ガス炉では、制御棒要素,炉心拘束ベルト,タイロッド,上部プレナムシュラウド,高温ダクト断熱カバー材,床ブロック等への適用が検討されている。しかし、C/C複合材料は400C以上で酸化されやすいので、空気進入事故を想定したヘリウム環境下又は空気環境下での酸化挙動及び特性の低下を、実際に使用する前に評価する必要がある。本研究では、数種類の原子炉級C/C複合材料の酸化挙動をさまざまな温度条件で評価した。酸化試験は、酸化温度500から1100Cの範囲で空気又はアルゴン雰囲気で行った。また、酸化前後の熱拡散率,曲げ強度,引張強度及び層間強度を評価した。

Carbon-carbon (C/C) composites have been widely used for high-temperature structural applications because they possess excellent mechanical properties such as high specific strength and thermal shock resistance. In the nuclear industry, the composites have also been considered for plasma facing materials in fusion reactors and high-temperature structural parts in gas cooled reactors. In the high-temperature gas cooled reactor, the composites are being considered for the application of various high-temperature structural parts such as control rod components, core restraint belts, tie rods, upper plenum shroud, hot duct insulation cover sheets, and floor blocks. However, the carbon based materials are susceptible to oxidation at temperatures above 400 C. Therefore, the oxidation behavior and property degradation at high temperature under impure He or in air in case of accidental air ingress should be evaluated before the deployment of composites. In this study, the oxidation behavior of several nuclear-grade C/C composites was evaluated at various temperatures. Thermal and mechanical properties of the composites were also measured before and after oxidation. The oxidation experiments were performed in range of 500 to 1100 C under air or Ar atmosphere. Thermal diffusivity, flexural strength, tensile strength, and interlaminar shear strength of as-received and oxidized specimens were evaluated.