INFLUENCE OF LOCALIZED PLASTICITY ON IASCC SENSITIVITY OF AUSTENITIC STAINLESS STEELS UNDER PWR PRIMARY WATER.

被引:0
|
作者
Cisse, Sarata [1 ]
Tanguy, Benoit [1 ]
Laffont, Lydia [2 ]
Lafont, Marie-Christine [2 ]
Guerre, Catherine [3 ]
Andrieu, Eric [2 ]
机构
[1] CEA Saclay, Nucl Mat Dept, F-91191 Gif Sur Yvette, France
[2] Inst CARNOT, CIRMAT ENSIACET, F-31030 Toulouse, France
[3] CEA, DEN DPC, SCCME, Lab Etud Corros, F-91191 Gif Sur Yvette, France
来源
15TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS | 2011年
关键词
irradiation assisted stress corrosion cracking (IASCC); plastic deformation localization; precipitation strengthened stainless steel A286; DEFORMATION; 304-STAINLESS-STEEL; MICROSTRUCTURE; INITIATION; MECHANISM;
D O I
暂无
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The sensibility of precipitation-strengthened A286 austenitic stainless steel to Stress Corrosion Cracking (SCC) is studied by means of Slow Strain Rate Tests (SSRT). First, alloy cold working by Low Cycle Fatigue (LCF) is investigated. Fatigue tests under plastic strain control are performed at different strain levels (Delta epsilon(p)/2=0.2%, 0.5% and 0.8%) in order to establish correlation between stress softening and deformation microstructure resulting from LCF tests. Deformed microstructures have been identified through TEM investigations. Three states of cyclic behaviour for precipitation-strengthened A286 have been identified: hardening, cyclic softening and finally saturation of softening. It is shown that the A286 alloy cyclic softening is due to microstructural features such as defects - free deformation bands resulting from dislocations motion along family plans < 111>, that swept defects or gamma' precipitates and lead to deformation localization. In order to quantify effects of plastic localized deformation on intergranular stress corrosion cracking (IGSCC) of the A286 alloy in PWR primary water, slow strain rate tests are conducted. For each cycling conditions, two specimens at a similar stress level are tested: the first containing free precipitate deformation bands, the other not significant of a localized deformation state. SSRT tests are still in progress.
引用
收藏
页码:1417 / 1427
页数:11
相关论文
共 12 条
  • [1] Influence of localized plasticity on oxidation behaviour of austenitic stainless steels under primary water reactor
    Cisse, Sarata
    Laffont, Lydia
    Lafont, Marie-Christine
    Tanguy, Benoit
    Andrieu, Eric
    JOURNAL OF NUCLEAR MATERIALS, 2013, 433 (1-3) : 319 - 328
  • [2] Impact of localized deformation on IASCC in austenitic stainless steels
    Jiao, Z.
    Was, G. S.
    JOURNAL OF NUCLEAR MATERIALS, 2011, 408 (03) : 246 - 256
  • [3] A review of stress corrosion cracking of austenitic stainless steels in PWR primary water
    Ehrnsten, Ulla
    Andresen, Peter L.
    Que, Zaiqing
    JOURNAL OF NUCLEAR MATERIALS, 2024, 588
  • [4] Corrosion fatigue and microstructural characterisation of Type 316 austenitic stainless steels tested in PWR primary water
    Mukahiwa, K.
    Scenini, F.
    Burke, M. G.
    Platts, N.
    Tice, D. R.
    Stairmand, J. W.
    CORROSION SCIENCE, 2018, 131 : 57 - 70
  • [5] Quantification of SCC mechanisms in austenitic alloys under PWR primary water conditions
    Lozano-Perez, Sergio
    Roberts, Ed
    Karamched, Phani
    Shen, Zhao
    CORROSION REVIEWS, 2024, 42 (05) : 565 - 584
  • [6] Effects of long-term thermal aging on the stress corrosion cracking behavior of cast austenitic stainless steels in simulated PWR primary water
    Li, Shilei
    Wang, Yanli
    Wang, Hui
    Xin, Changsheng
    Wang, Xitao
    JOURNAL OF NUCLEAR MATERIALS, 2016, 469 : 262 - 268
  • [7] Influence of Irradiation on the Oxide Film Formed on 316 L Stainless Steel in PWR Primary Water
    Perrin, Stephane
    Marchetti, Loic
    Duhamel, Cecilie
    Sennour, Mohamed
    Jomard, Francois
    OXIDATION OF METALS, 2013, 80 (5-6): : 623 - 633
  • [8] Proton irradiation assisted localized corrosion and stress corrosion cracking in 304 nuclear grade stainless steel in simulated primary PWR water
    Deng, Ping
    Peng, Qunjia
    Han, En-Hou
    Ke, Wei
    Sun, Chen
    JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2021, 65 : 61 - 71
  • [9] Effect of surface preparation on the corrosion of austenitic stainless steel 304L in high temperature steam and simulated PWR primary water
    Cisse, Sarata
    Laffont, Lydia
    Tanguy, Benoit
    Lafont, Marie-Christine
    Andrieu, Eric
    CORROSION SCIENCE, 2012, 56 : 209 - 216
  • [10] The influence of stacking fault energy on plasticity mechanisms in triode-plasma nitrided austenitic stainless steels: Implications for the structure and stability of nitrogen-expanded austenite
    Tao, Xiao
    Liu, Xingguang
    Matthews, Allan
    Leyland, Adrian
    ACTA MATERIALIA, 2019, 164 : 60 - 75