Strain-based plastic instability acceptance criteria for ferritic steel safety class 1 nuclear components under level D service loads

Ji Su Kim, Han Sang Lee, Jong Sung Kim, Yun Jae Kim, Jin Won Kim

研究成果: Article査読

6 被引用数 (Scopus)

抄録

This paper proposes strain-based acceptance criteria for assessing plastic instability of the safety class 1 nuclear components made of ferritic steel during level D service loads. The strain-based criteria were proposed with two approaches: (1) a section average approach and (2) a critical location approach. Both approaches were based on the damage initiation point corresponding to the maximum load-carrying capability point instead of the fracture point via tensile tests and finite element analysis (FEA) for the notched specimen under uni-axial tensile loading. The two proposed criteria were reviewed from the viewpoint of design practice and philosophy to select a more appropriate criterion. As a result of the review, it was found that the section average approach is more appropriate than the critical location approach from the viewpoint of design practice and philosophy. Finally, the criterion based on the section average approach was applied to a simplified reactor pressure vessel (RPV) outlet nozzle subject to SSE loads. The application shows that the strain-based acceptance criteria can consider cumulative damages caused by the sequential loads unlike the stress-based acceptance criteria and can reduce the overconservatism of the stress-based acceptance criteria, which often occurs for level D service loads.

本文言語English
ページ(範囲)340-350
ページ数11
ジャーナルNuclear Engineering and Technology
47
3
DOI
出版ステータスPublished - 2015
外部発表はい

ASJC Scopus subject areas

  • 原子力エネルギーおよび原子力工学

フィンガープリント

「Strain-based plastic instability acceptance criteria for ferritic steel safety class 1 nuclear components under level D service loads」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