Prediction of fracture toughness of reactor pressure vessel steels on the basis of the 'Master Curve' approach and the probabilistic model

被引:0
|
作者
Margolin, B.Z. [1 ]
Shvetsova, V.A. [1 ]
Gulenko, A.G. [1 ]
Il'in, A.V. [1 ]
Nikolaev, V.A. [1 ]
Smirnov, V.I. [1 ]
机构
[1] TsNII KM 'Prometej', Sankt-Peterburg, Russia
来源
Problemy Prochnosti | 2002年 / 01期
关键词
Calculations - Embrittlement - Fracture toughness - Materials testing - Mathematical models - Nuclear reactors - Pressure vessels - Steel construction - Thermal effects;
D O I
暂无
中图分类号
学科分类号
摘要
On the basis of a probabilistic model and 'Master Curve' approach we perform prediction of the brittle fracture-toughness temperature dependence of 15Kh2NMFA reactor pressure-vessel steel in the initial and high-embrittled states. The K1c(T) curves for the initial state calculated with the Master Curve approach and the probabilistic model are compared and their good agreement is shown. Experimental values of the fracture toughness have been obtained for the embrittled 15Kh2NMFA steel through testing compact-tension specimens over a wide temperature range. It is shown that the K1c(T) curve for the embrittled steel calculated in accordance with the Master curve approach does not describe the experimental data adequately. At the same time, the agreement of the experimental data on fracture toughness and the K1c(T) curves calculated by the probabilistic model is good.
引用
收藏
页码:5 / 21
相关论文
共 50 条
  • [1] Prediction of fracture toughness of reactor pressure-vessel steels using the “master curve" concept and probabilistic model
    Margolin B.Z.
    Shvetsova V.A.
    Gulenko A.G.
    Il’In A.V.
    Nikolaev V.A.
    Smirnov V.I.
    Strength of Materials, 2002, 34 (1) : 1 - 11
  • [2] Fracture toughness predictions for a reactor pressure vessel steel in the initial and highly embrittled states with the Master Curve approach and a probabilistic model
    Margolin, BZ
    Shvetsova, VA
    Gulenko, AG
    Ilyin, AV
    Nikolaev, VA
    Smirnov, VI
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2002, 79 (03) : 219 - 231
  • [3] Improved probabilistic model for fracture toughness prediction for nuclear pressure vessel steels
    Central Research Inst of Structural, Materials `Prometey', St. Petersburg, Russia
    Int J Pressure Vessels Piping, 12 (843-855):
  • [4] Improved probabilistic model for fracture toughness prediction for nuclear pressure vessel steels
    Margolin, BZ
    Gulenko, AG
    Shvetsova, VA
    INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1998, 75 (12) : 843 - 855
  • [5] Assessment of the master curve approach on three reactor pressure vessel steels
    Lucon, E
    Scibetta, M
    Van Walle, E
    INTERNATIONAL JOURNAL OF FRACTURE, 2003, 119 (02) : 161 - 178
  • [6] Assessment of the master curve approach on three reactor pressure vessel steels
    Enrico Lucon
    Marc Scibetta
    Eric Van Walle
    International Journal of Fracture, 2003, 119 : 161 - 178
  • [7] MASTER CURVE APPROACH FOR SOME JAPANESE REACTOR PRESSURE VESSEL STEELS
    Tomimatsu, Minoru
    Hirano, Takashi
    Asada, Seiji
    Saeki, Ryoichi
    Miura, Naoki
    Yamashita, Norimichi
    Yonehara, Akira
    Saito, Itaru
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2008, VOL 6, PT A AND B, 2009, : 855 - 862
  • [8] FRACTURE TOUGHNESS EVALUATION OF REACTOR PRESSURE VESSEL STEELS BY MASTER CURVE METHOD USING MINI-CT SPECIMENS
    Tobita, Tohru
    Nishiyama, Yutaka
    Ohtsu, Takuyo
    Udagawa, Makoto
    Katsuyama, Jinya
    Onizawa, Kunio
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE - 2013, VOL 1B: CODES AND STANDARDS, 2014,
  • [9] Fracture Toughness Evaluation of Reactor Pressure Vessel Steels by Master Curve Method Using Miniature Compact Tension Specimens
    Tobita, Tohru
    Nishiyama, Yutaka
    Ohtsu, Takuyo
    Udagawa, Makoto
    Katsuyama, Jinya
    Onizawa, Kunio
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 2015, 137 (05):
  • [10] Investigation of loading rate effect on cleavage fracture toughness of reactor pressure vessel steels based on master curve method
    Sun, Ying-Xue
    Onizawa, Kunio
    Hedongli Gongcheng/Nuclear Power Engineering, 2003, 24 (03): : 227 - 230