メインナビゲーションにスキップ 検索にスキップ メインコンテンツにスキップ

Pwscc initiation of alloy 600: effect of long-term thermal aging and triaxial stress

  • Seung Chang Yoo
  • , Kyoung Joon Choi
  • , Seunghyun Kim
  • , Ji Soo Kim
  • , Byoung Ho Choi
  • , Yun Jae Kim
  • , Jong Sung Kim
  • , Ji Hyun Kim

研究成果: Conference contribution

抄録

Thermally aged nickel based Alloy 600 was investigated to evaluate the effects of long-term thermal aging and triaxial stress on primary water stress corrosion crack initiation behavior. Long-term thermal aging was simulated by heat treatment at 400 °C, a temperature that does not cause excessive formation of second phases that cannot form in nuclear power plant service conditions. Triaxial stress was applied by a round notch in the gauge length of some test specimen; other specimens were smooth. Slow strain rate tests (SSRT) monitored by the direct current potential drop method were conducted to evaluate stress corrosion crack initiation susceptibility of the thermally aged specimens in the primary water environment. For smooth specimens (which experience uniaxial stress), the susceptibility of those thermally aged for the equivalent of 10-years was the highest, while the susceptibility of the as-received specimens was the lowest. However, for the notched specimens (which experience triaxial stress), the specimens thermally aged for the equivalent of 20-years showed the highest susceptibility, while the as-received specimens showed the lowest.

本文言語English
ホスト出版物のタイトルMinerals, Metals and Materials Series
出版社Springer International Publishing
ページ281-292
ページ数12
ISBN(印刷版)9783030046385, 9783030046392, 9783319515403, 9783319651354, 9783319728520, 9783319950211
DOI
出版ステータスPublished - 2019
イベント18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019 - Boston, United States
継続期間: 2019 8月 18 → 2019 8月 22

出版物シリーズ

名前Minerals, Metals and Materials Series
ISSN(印刷版)2367-1181
ISSN(電子版)2367-1696

Conference

Conference18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors 2019
国/地域United States
CityBoston
Period19/8/18 → 19/8/22

ASJC Scopus subject areas

  • 電子材料、光学材料、および磁性材料
  • エネルギー工学および電力技術
  • 材料力学
  • 金属および合金
  • 材料化学

フィンガープリント

「Pwscc initiation of alloy 600: effect of long-term thermal aging and triaxial stress」の研究トピックを掘り下げます。これらがまとまってユニークなフィンガープリントを構成します。

引用スタイル