Residual Stresses in Clad Nuclear Reactor Pressure Vessel Steels: Prediction, Measurement and Reconstruction

被引:0
|
作者
Serasli, Karim [1 ]
Coules, Harry [1 ]
Smith, David [1 ]
机构
[1] Univ Bristol, Dept Mech Engn, Bristol BS8 1TR, Avon, England
关键词
LIMITED MEASUREMENTS;
D O I
暂无
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
Most residual stress measurement methods are limited in terms of their stres and spatial resolution, number of stress tensor components measured and measurement uncertainty. In contrast, finite element simulations of welding processes provide full field distributions of residual stresses, with results dependent on the quality of the input conditions. Measurements and predictions are often not the same, and the true residual stress state is difficult to determine. In this paper both measurements and predictions of residual stresses, created in clad nuclear reactor pressure vessel steels, are made. The measurements are then used as input to a residual stress mapping technique provided within a finite element analysis. The technique is applied iteratively to converge to a balanced solution which is not necessarily unique. However, the technique aids the identification of locations for additional measurements. This is illustrated in the paper. The outcomes from the additional measurements permit more realistic and reliable estimates of the true residual state to be made. The outcomes are compared with the finite element simulations of the welding process and used to determine whether there is a need for additional input to the simulations.
引用
收藏
页数:12
相关论文
共 50 条
  • [1] Intergranular Embrittlement of Nuclear Reactor Pressure Vessel Steels
    Zabusov, Oleg O.
    Gurovich, Boris A.
    Kuleshova, Evgenia A.
    Saltykov, Michail A.
    Fedotova, Svetlana V.
    Dementjev, Alexey P.
    [J]. MATERIALS STRUCTURE & MICROMECHANICS OF FRACTURE VII, 2014, 592-593 : 577 - 581
  • [2] A comparison of western and eastern nuclear reactor pressure vessel steels
    Davies, LM
    [J]. INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 1999, 76 (03) : 163 - 208
  • [3] Positron annihilation measurements on nuclear reactor pressure vessel steels
    [J]. 1600, Editions de Physique, Les Ulis, France (05):
  • [4] Effects of embedded cracks and residual stresses on the integrity of a reactor pressure vessel
    Qian, Guian
    Gonzalez-Albuixech, V. F.
    Niffenegger, Markus
    [J]. ENGINEERING FAILURE ANALYSIS, 2018, 90 : 451 - 462
  • [5] ROLE OF RESIDUAL STRESSES AND STRAINS FIELDS GENERATED BY HEAT TREATMENTS ON THE HYDROGEN EMBRITTLEMENT OF A NUCLEAR REACTOR PRESSURE VESSEL
    Toribio, J.
    Vergara, D.
    Lorenzo, M.
    Martin, J. J.
    [J]. PROCEEDINGS OF THE ASME SMALL MODULAR REACTORS SYMPOSIUM (SMR 2011), 2012, : 137 - 143
  • [6] Measurement of welding residual stresses of reactor vessel by inherent strain method: Measurement of residual stresses of pipe-plate penetration joint
    Nakacho, Keiji
    Ohta, Takahiro
    Ogawa, Naoki
    Ma, Ninshu
    Hamaguchi, Hiromitsu
    Satou, Mineki
    Nayama, Michisuke
    [J]. Welding International, 2009, 23 (06) : 439 - 449
  • [7] NEW ALLOY STEELS FOR NUCLEAR REACTOR PRESSURE VESSELS AND VESSEL INTERNALS
    GROUNES, M
    RAO, S
    [J]. ASM TRANSACTIONS QUARTERLY, 1969, 62 (04): : 902 - &
  • [8] PREDICTION OF RADIATION EMBRITTLEMENT FOR HIGHLY IRRADIATED REACTOR PRESSURE VESSEL STEELS
    Matsuzawa, Hiroshi
    [J]. ASME PRESSURE VESSELS AND PIPING CONFERENCE 2009, VOL 1: CODES AND STANDARDS, 2010, : 429 - 433
  • [9] Prediction of the effects of thermal ageing on the embrittlement of reactor pressure vessel steels
    Margolin, B. Z.
    Yurchenko, E. V.
    Morozov, A. M.
    Chistyakov, D. A.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2014, 447 (1-3) : 107 - 114
  • [10] Redistribution of residual stress by thermal shock in reactor pressure vessel steel clad with nickel alloy
    Oliver, Sam J.
    Mostafavi, Mahmoud
    Hosseinzadeh, Foroogh
    Pavier, Martyn J.
    [J]. INTERNATIONAL JOURNAL OF PRESSURE VESSELS AND PIPING, 2019, 169 : 37 - 47