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
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 50 条
  • [31] Modeling of microstructure evolution in austenitic stainless steels irradiated under light water reactor conditions
    Gan, J
    Was, GS
    Stoller, RE
    MICROSTRUCTURAL PROCESSES IN IRRADIATED MATERIALS, 1999, 540 : 439 - 444
  • [32] Corrosion Behavior of Stainless Steels in Simulated PWR Primary Water -Effect of Chromium Content in Alloys and Dissolved Hydrogen
    Terachi, Takumi
    Yamada, Takuyo
    Miyamoto, Tomoki
    Arioka, Koji
    Fukuyai, Koji
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 2008, 45 (10) : 975 - 984
  • [33] 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
  • [34] Influence of Irradiation on the Oxide Film Formed on 316 L Stainless Steel in PWR Primary Water
    Stéphane Perrin
    Loic Marchetti
    Cécilie Duhamel
    Mohamed Sennour
    François Jomard
    Oxidation of Metals, 2013, 80 : 623 - 633
  • [35] Influence of surface morphology and roughness on water wetting properties of low temperature nitrided austenitic stainless steels
    Borgioli, Francesca
    Galvanetto, Emanuele
    Bacci, Tiberio
    MATERIALS CHARACTERIZATION, 2014, 95 : 278 - 284
  • [36] Corrosion fatigue crack growth behaviour of austenitic stainless steels under light water reactor conditions
    Seifert, H. P.
    Ritter, S.
    Leber, N. J.
    CORROSION SCIENCE, 2012, 55 : 61 - 75
  • [37] INFLUENCE OF PWR PRIMARY WATER ON LCF BEHAVIOR OF TYPE 304L AUSTENITIC STAINLESS STEEL AT 300°C - COMPARISON WITH RESULTS OBTAINED IN VACUUM OR IN AIR
    De Baglion, Laurent
    Mendez, Jose
    Le Duff, Jean-Alain
    Lefrancois, Andre
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, PVP 2012, VOL 3, 2012, : 463 - 472
  • [38] EFFECTS OF THERMO-MECHANICAL TREATMENTS ON DEFORMATION BEHAVIOR AND IGSCC SUSCEPTIBILITY OF STAINLESS STEELS IN PWR PRIMARY WATER CHEMISTRY
    Nouraei, S.
    Tice, D. R.
    Mottershead, K. J.
    Wright, D. M.
    15TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, 2011, : 2381 - 2401
  • [39] ANALYSIS OF ENVIRONMENTAL FATIGUE CRACK GROWTH BEHAVIOR OF TYPE 347 STAINLESS STEELS UNDER SIMULATED PWR WATER CONDITIONS
    Hong, Seokmin
    Min, Ki-Deuk
    Jeon, Soon-Hyeok
    Lee, Bong-Sang
    PROCEEDINGS OF THE ASME PRESSURE VESSELS AND PIPING CONFERENCE, 2017, VOL 1A, 2017,
  • [40] Influence of silicon, carbon and phosphorus on intergranular corrosion of high purity austenitic stainless steels under transpassive conditions
    Stolarz, J.
    Journal De Physique, 1995, 5 (07): : 7 - 423