Characterization of fatigue property for 316FR at elevated temperatures

被引:0
|
作者
Kobayashi K. [1 ]
Hayakawa M. [1 ]
Kimura M. [1 ]
Yamaguchi K. [1 ]
机构
[1] National Institute for Materials Science, Tsukuba 305-0047, 1-2-1, Sengen
关键词
316; steel; elevated temperature; Fatigue; fractography; low-cycle; strain rate;
D O I
10.3233/SFC-2010-0111
中图分类号
学科分类号
摘要
Type 316FR stainless steel has been developed as a candidate material for fast breeder reactors. To ensure the structural integrity at high temperature of the reactor components including the reactor vessel, long-term data and an analysis method are investigated for 316FR steel to evaluate time-dependent low-cycle fatigue behavior. The present study reports the dependence from 550 to 600°C. Data are analyzed using a parameter method previously proposed by the authors. It is shown that the method effectively predicts fatigue life even at a very low strain rate of 10-6/s. © 2010 IOS Press and the authors. All rights reserved.
引用
收藏
页码:129 / 139
页数:10
相关论文
共 50 条
  • [1] Study on environmental effect on fatigue and creep-fatigue strength of 316FR stainless steel in sodium at elevated temperature
    Date, Shingo
    Ishikawa, Hiroshi
    Otani, Tornorni
    Takahashi, Yukio
    Nakazawa, Takanori
    NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (02) : 353 - 367
  • [2] EVALUATION METHOD OF CREEP-FATIGUE LIFE FOR 316FR WELDMENT
    Nagae, Yuji
    Yamamoto, Kenji
    Otani, Tomomi
    ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2015, VOL 6A, 2015,
  • [3] Effect of ratcheting deformation on fatigue and creep-fatigue life of 316FR stainless steel
    Date, Shingo
    Ishikawa, Hiroshi
    Otani, Tomorni
    Takahashi, Yukio
    NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (02) : 336 - 346
  • [4] Clarification of strain limits considering the ratcheting fatigue strength of 316FR steel
    Isobe, Nobuhiro
    Sukekawa, Masayuki
    Nakayama, Yasunari
    Date, Shingo
    Ohtani, Tomorni
    Takahashi, Yukio
    Kasahara, Naoto
    Shibamoto, Hiroshi
    Nagashima, Hideaki
    Inoue, Kazuhiko
    NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (02) : 347 - 352
  • [5] Development of Creep-Fatigue Evaluation Method for 316FR Stainless Steel
    Nagae, Yuji
    Takaya, Shigeru
    Asayama, Tai
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2015, 137 (04):
  • [6] Strength of 316FR Joints Welded by Type 316FR/16-8-2 Filler Metals
    Yamashita, Takuya
    Nagae, Yuji
    Satoh, Kenichiro
    Yamamoto, Kenji
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2016, 138 (02):
  • [7] Helium effects on the tensile property of 316FR stainless steel at 650 and 750 °C
    Imasaki, Kazuto
    Hasegawa, Akira
    Nogami, Shuhei
    Satou, Manabu
    JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) : 1030 - 1033
  • [8] Prediction of σ-Phase Embrittlement in Type 316FR Weld Metal
    Chun, E. J.
    Baba, H.
    Terashima, K.
    Nishimoto, K.
    Saida, K.
    WELDING JOURNAL, 2013, 92 (05) : 133S - 139S
  • [9] High-Temperature Helium Embrittlement of 316FR Steel
    Nogami, Shuhei
    Hasegawa, Akira
    Tanno, Takashi
    Imasaki, Kazuto
    Abe, Kazuma
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2011, 48 (01) : 130 - 134
  • [10] Study on creep-fatigue life prediction methods for low-carbon nitrogen-controlled 316 stainless steel (316FR)
    Takahashi, Yukio
    Shibarnoto, Hiroshi
    Inoue, Kazuhiko
    NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (02) : 322 - 335