Influence of irradiation on the ductile fracture of a reactor pressure vessel steel

被引：6
|
作者：
Hausild, P
Kytka, M
Karlík, M
Pesek, P
机构：
[1] Czech Tech Univ, Dept Mat, Fac Nucl Sci & Phys Engn, Prague 12000 2, Czech Republic
[2] Inst Nucl Res, Integr & Tech Engn Div, Rez 25068, Czech Republic
来源：
JOURNAL OF NUCLEAR MATERIALS | 2005年 / 341卷 / 2-3期
关键词：
D O I：
10.1016/j.jnucmat.2005.01.019
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The mechanical properties of 15Ch2MFA steel were characterised by tensile and instrumented Charpy tests. The fracture surfaces of Charpy specimens broken in the ductile-to-brittle transition temperature range contain a certain proportion of ductile fracture correlated to fracture energy. Measured ductile crack lengths show the same dependence on fracture deflection and/or fracture energy for irradiated and non-irradiated specimens. The decrease of upper shelf energy with increasing neutron fluence could be explained by an increasing amount of shear fracture. (c) 2005 Elsevier B.V. All rights reserved.
引用
收藏
页码：184 / 188
页数：5
相关论文
共 50 条
  • [41] A study on initial formation stage of proton irradiation defects in reactor pressure vessel steel
    Hao, Ting
    Liu, Xueqing
    Zhou, Bijin
    Li, Yuanfei
    Xu, Chaoliang
    Liu, Xiangbing
    Jiang, Weibin
    Fang, Qianfeng
    Zhang, Tao
    NUCLEAR MATERIALS AND ENERGY, 2024, 41
  • [42] Identification of ductile damage parameters for pressure vessel steel
    Dzugan, Jan
    Spaniel, Miroslav
    Prantl, Antonin
    Konopik, Pavel
    Ruzicka, Jan
    Kuzelka, Jiri
    NUCLEAR ENGINEERING AND DESIGN, 2018, 328 : 372 - 380
  • [43] REACTOR SURVEILLANCE TEST AND FRACTURE-MECHANICS EVALUATION OF IRRADIATION EMBRITTLEMENT IN REACTOR PRESSURE-VESSEL STEELS
    TAKAHASHI, H
    SAITO, K
    SHOJI, T
    DATE, K
    SUZUKI, M
    JOURNAL OF ENGINEERING MATERIALS AND TECHNOLOGY-TRANSACTIONS OF THE ASME, 1980, 102 (04): : 317 - 326
  • [44] FRACTURE TOUGHNESS OF HEAVY SECTION STEEL FOR NUCLEAR-REACTOR PRESSURE-VESSEL
    SUSUKIDA, H
    SUNAMOTO, D
    SATOH, M
    FUNADA, T
    TRANSACTIONS OF THE IRON AND STEEL INSTITUTE OF JAPAN, 1977, 17 (09) : 497 - 505
  • [45] Fatigue fracture features of pressure vessel steel in simulated light water reactor environment
    Lee, SG
    Kim, IS
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2001, 38 (02) : 120 - 126
  • [46] FRACTURE BEHAVIOR OF REACTOR PRESSURE-VESSEL STEEL IN FRANGIBLE, TRANSITIONAL AND TOUGH REGIMES
    WITT, FJ
    NUCLEAR ENGINEERING AND DESIGN, 1972, 20 (01) : 237 - &
  • [47] LOWER-BOUND FRACTURE-TOUGHNESS OF A REACTOR-PRESSURE-VESSEL STEEL
    ROSENFIELD, AR
    SHETTY, DK
    ENGINEERING FRACTURE MECHANICS, 1981, 14 (04) : 833 - &
  • [48] On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models
    Odette, G. R.
    Yamamoto, T.
    Williams, T. J.
    Nanstad, R. K.
    English, C. A.
    JOURNAL OF NUCLEAR MATERIALS, 2019, 526
  • [49] Protecting reactor pressure vessels against brittle fracture and ductile fracture
    Evers, HO
    ATW-INTERNATIONALE ZEITSCHRIFT FUR KERNENERGIE, 1996, 41 (06): : 406 - 410
  • [50] Use of Local Approach for Prediction of the Irradiation Effect on Fracture Toughness of Pressure Vessel Steel
    Sergiy, Kotrechko
    Sergii, Mamedov
    Ivo, Dlouhy
    Vladislav, Kozak
    MATERIALS STRUCTURE & MICROMECHANICS OF FRACTURE, 2011, 465 : 568 - +
12345