[논문]Proton Irradiation Effects on Hardness and the Volta Potential of Welding 308L Duplex Stainless Steel

Jiang, Baolong; Peng, Qunjia; Jiao, Zhijie; Volinsky, Alex A.; Qiao, Lijie

doi:10.3390/mi10010011

Proton Irradiation Effects on Hardness and the Volta Potential of Welding 308L Duplex Stainless Steel 원문보기

Micromachines, v.10 no.1, 2019년, pp.11 -

Jiang, Baolong (Beijing Advanced Innovation Center for Material Genetic Engineering, Key Laboratory for Environmental Fracture (MOE), University of Science and Technology Beijing, Beijing 100083, China) , Peng, Qunjia (jiangbaolong@xs.ustb.edu.cn (B.J.)) , Jiao, Zhijie (volinsky@usf.edu (A.A.V.)) , Volinsky, Alex A. (Key Laboratory of Nuclear Materials and Safety Assessment, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China) , Qiao, Lijie (pengqunjia@cgnpc.com.cn)

Abstract ▼ AI-Helper

308L welding duplex stainless steel has been irradiated at 360 °C with 2 MeV protons, corresponding to a dose of 3 dpa at the maximum depth of 20 μm. Microhardness of the δ-ferrite and austenite phases was studied before and after proton irradiation using in situ nanomechanical test system (ISNTS). The locations of the phases for indentations placement were obtained by scanning probe microscopy from the ISNTS. The hardness of the δ-ferrite had a close relationship with the vacancy distribution obtained from the Stopping and Range of Ions in Matter (SRIM) Monte Carlo simulation code. However, the hardness of the austenite phase in the maximum damage region (17–20 μm depth) from the SRIM simulation was decreasing sharply, and a hardness transition region (>20 μm and 20 μm depth). However, the δ-ferrite hardness behavior was different. A hardness of the two phases increased on the irradiated surface and the interior due to different hardening mechanisms in the austenite and δ-ferrite phases after a long time high-temperature irradiation. A transition region (>20 μm and <55 μm depth) of the Volta potential was also found, which was caused by the deeper transfer of implanted protons measured by scanning Kelvin probe force microscopy.

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참고문헌 (64)

1. Scott P. A review of irradiation assisted stress corrosion cracking J. Nucl. Mater. 1994 211 101 122 10.1016/0022-3115(94)90360-3

상세보기
2. Gamer F.A. Makenas B.J. Chastain S.A. Swelling and creep observed in AISI 304 fuel pin cladding from three MOX fuel assemblies irradiated in EBR-II J. Nucl. Mater. 2011 413 53 61

상세보기
3. Zinkle S.J. Was G.S. Materials challenges in nuclear energy Acta Mater. 2013 61 735 758 10.1016/j.actamat.2012.11.004

상세보기
4. Azevedo C.R.F. A review on neutron-irradiation-induced hardening of metallic components Eng. Failure Anal. 2011 18 1921 1942 10.1016/j.engfailanal.2011.06.008

상세보기
5. Gaumé M. Baldo P. Mompiou F. Onimus F. In-situ observation of an irradiation creep deformation mechanism in zirconium alloys Scr. Mater. 2018 154 87 91 10.1016/j.scriptamat.2018.05.030

상세보기
6. Xu C. Zhang X. Chen Y.-R. Li M.-M. Park J.S. Kenesei P. Almer J. Yang Y. In-situ high-energy X-ray characterization of neutron irradiated HT-UPS stainless steel under tensile deformation Acta Mater. 2018 156 330 341 10.1016/j.actamat.2018.07.008

상세보기
7. Stephenson K.J. Was G.S. The role of dislocation channeling in IASCC initiation of neutron irradiated stainless steel J. Nucl. Mater. 2016 481 214 225 10.1016/j.jnucmat.2016.09.001

상세보기
8. Jiao Z. Was G.S. Localized deformation and IASCC initiation in austenitic stainless steels J. Nucl. Mater. 2008 382 203 209 10.1016/j.jnucmat.2008.08.032

상세보기
9. Gupta J. Hure J. Tanguy B. Laffont L. Lafont M.-C. Andrieu E. Evaluation of stress corrosion cracking of irradiated 304L stainless steel in PWR environment using heavy ion irradiation J. Nucl. Mater. 2016 476 82 92 10.1016/j.jnucmat.2016.04.003

상세보기
10. Zhu T. Wang B.-Y. Yuan D.-Q. Jin S.-X. Zhang P. Lu E.-Y. Song L.-G. Liu Y.-L. Ma H.-L. Zhang Q.-L. Effect of temperature and dose on vacancy-defect evolution in 304L stainless steel irradiated by triple ion beam J. Nucl. Mater. 2018 512 94 99 10.1016/j.jnucmat.2018.10.007

상세보기
11. Renault-Laborne A. Hure J. Malaplate J. Gavoille P. Sefta F. Tanguy B. Tensile properties and deformation microstructure of highly neutronirradiated 316 stainless steels at low and fast strain rate J. Nucl. Mater. 2018 508 488 504 10.1016/j.jnucmat.2018.05.068

상세보기
12. Meric de Bellefon G. Van Duysen J.C. Tailoring plasticity of austenitic stainless steels for nuclear applications: Review of mechanisms controlling plasticity of austenitic steels below 400 °C J. Nucl. Mater. 2016 475 168 191 10.1016/j.jnucmat.2016.04.015

상세보기
13. Duan B.-H. Heintze C. Bergner F. Ulbricht A. Akhmadaliev S. Onorbe E. Carlan Y.D. Wang T. The effect of the initial microstructure in terms of sink strength on the ion-irradiation-induced hardening of ODS alloys studied by Nano indentation J. Nucl. Mater. 2017 495 118 127 10.1016/j.jnucmat.2017.08.014

상세보기
14. Gao R. Zhang T. Wang X.-P. Fang Q.-F. Liu C.-S. Effect of zirconium addition on the microstructure and mechanical properties of ODS ferritic steels containing aluminum J. Nucl. Mater. 2014 444 462 468 10.1016/j.jnucmat.2013.10.038

상세보기
15. Jiang S.-N. Xu L.-Q. Zheng P.-F. Evaluation of hardening behavior under synergistic interaction of He and subsequent H ions irradiation in vanadium alloys Nucl. Mater. Energy. 2018 16 19 23 10.1016/j.nme.2018.06.008

상세보기
16. Kiran Kumar N.A.P. Li C. Leonard K.J. Bei H. Zinkle S.J. Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation Acta Mater. 2016 113 230 244 10.1016/j.actamat.2016.05.007

상세보기
17. Jin K. Guo W. Lu C.-Y. Ullah M.W. Zhang Y.-W. Weber W.J. Wang L.-M. Poplawsky J.D. Bei H.-B. Effects of Fe concentration on the ion-irradiation induced defect evolution and hardening in Ni-Fe solid solution alloys Acta Mater. 2016 121 365 373 10.1016/j.actamat.2016.09.025

상세보기
18. Marini B. Averty X. Wident P. Forget P. Barcelo F. Effect of the bainitic and martensitic microstructures on the hardening and embrittlement under neutron irradiation of a reactor pressure vessel steel J. Nucl. Mater. 2015 465 20 27 10.1016/j.jnucmat.2015.05.023

상세보기
19. Kotrechko S. Dubinko V. Stetsenko N. Terentyev D. He X. Sorokin M. Temperature dependence of irradiation hardening due to dislocation loops and precipitates in RPV steels and model alloys J. Nucl. Mater. 2015 464 6 15 10.1016/j.jnucmat.2015.04.014

상세보기
20. Watanabe H. Masaki S. Masubuchi S. Yoshida N. Kamada Y. Radiation induced hardening of ion irradiated RPV steels J. Nucl. Mater. 2011 417 932 935 10.1016/j.jnucmat.2010.12.179

상세보기
21. Chopra O.K. Rao A.S. A review of irradiation effects on LWR core internal materials-IASCC susceptibility and crack growth rates of austenitic stainless steels J. Nucl. Mater. 2011 409 235 256 10.1016/j.jnucmat.2010.12.001

상세보기
22. Guzonas D. Novotny R. Penttilä S. Toivonen A. Zheng W.-Y. Radiation effects and mechanical properties Materials and Water Chemistry for Supercritical Water-Cooled Reactors Woodhead Publishing Cambridge, UK 2018 45 78
23. Zhao M.-Z. Liu F. Yang Z.-S. Xu Q. Ding F. Li X.-C. Zhou H.-S. Luo G.-N. Fluence dependence of helium ion irradiation effects on the microstructure and mechanical properties of tungsten Nucl. Instrum. Methods Phys. Res. Sect. B 2018 414 121 125 10.1016/j.nimb.2017.09.002

상세보기
24. Takeuchi T. Kakubo Y. Matsukawa Y. Nozawa Y. Toyama T. Nagai Y. Nishiyama Y. Katsuyama J. Yamaguchi Y. Onizawa K. Effects of thermal aging on microstructure and hardness of stainless steel weld-overlay cladding of nuclear reactor pressure vessels J. Nucl. Mater. 2014 452 235 240 10.1016/j.jnucmat.2014.04.003

상세보기
25. Takeuchi T. Kameda J. Nagai Y. Toyama T. Nishiyama Y. Onizawa K. Study on microstructural changes in thermally-aged stainless steel weld-overlay cladding of nuclear reactor pressure vessels by atom probe tomography J. Nucl. Mater. 2011 415 198 204 10.1016/j.jnucmat.2011.06.004

상세보기
26. Takeuchi T. Kakubo Y. Matsukawa Y. Nozawa Y. Toyama T. Nagai Y. Nishiyama Y. Katsuyama J. Yamaguchi Y. Onizawa K. Effects of neutron irradiation on microstructures and hardness of stainless steel weld-overlay cladding of nuclear reactor pressure vessels J. Nucl. Mater. 2014 449 273 276 10.1016/j.jnucmat.2014.01.004

상세보기
27. Pareige C. Novy S. Saillet S. Pareige P. Study of phase transformation and mechanical properties evolution of duplex stainless steel after long term thermal ageing (>20 years) J. Nucl. Mater. 2011 411 90 96 10.1016/j.jnucmat.2011.01.036

상세보기
28. Li Z.-B. Lo W.-Y. Chen W.-Y. Pakarinen J. Wu Y.-Q. Allen T. Irradiation response of delta ferrite in as-cast and thermally aged cast stainless steel J. Nucl. Mater. 2015 466 201 207 10.1016/j.jnucmat.2015.08.006

상세보기
29. Wu D. Zhang J. Huang J.-C. Bei H. Nieh T.G. Grain-boundary strengthening in nanocrystalline chromium and the Hall-Petch coefficient of body-centered cubic metals Scr. Mater. 2013 68 118 121 10.1016/j.scriptamat.2012.09.025

상세보기
30. Chen W.-Y. Li M.-M. Zhang X. Kirk M.A. Baldo P.M. Lian T. In situ TEM study of G-phase precipitates under heavy ion irradiation in CF8 cast austenitic stainless steel J. Nucl. Mater. 2015 464 185 192 10.1016/j.jnucmat.2015.04.042

상세보기
31. Chen W.-Y. Li M.-M. Kirk M.A. Baldo P.M. Lian T.-G. Effect of heavy ion irradiation on microstructural evolution in CF8 cast austenitic stainless steel J. Nucl. Mater. 2016 471 184 192 10.1016/j.jnucmat.2015.08.032

상세보기
32. Busby J.T. Hash M.C. Was G.S. The relationship between hardness and yield stress in irradiated austenitic and ferritic steels J. Nucl. Mater. 2005 336 267 278 10.1016/j.jnucmat.2004.09.024

상세보기
33. Fukuya K.J. Current understanding of radiation-induced degradation in light water reactor structural materials J. Nucl. Sci. Tech. 2013 50 213 254 10.1080/00223131.2013.772448

상세보기
34. Was G.S. Busby J.T. Allen T. Kenik E.A. Jensson A. Bruemmer S.M. Gan J. Edwards A.D. Scott P.M. Andreson P.L. Emulation of neutron irradiation effects with protons: Validation of principle J. Nucl. Mater. 2002 300 198 216 10.1016/S0022-3115(01)00751-6

상세보기
35. Murphy S.M. The influence of hydrogen on void swelling in fusion reactor materials J. Nucl. Mater. 1988 155–157 866 869 10.1016/0022-3115(88)90431-X

상세보기
36. Bullen D.B. Kulcinski G.L. Dodd R.A. Effect of hydrogen on void production in nickel J. Nucl. Mater. 1985 133–134 455 458 10.1016/0022-3115(85)90188-6

상세보기
37. Evers S. Senöz C. Rohwerder M. Hydrogen detection in metals: A review and introduction of a Kelvin prove approach Sci. Technol. Adv. Mater. 2013 14 1 12 10.1088/1468-6996/14/1/014201 27877549

상세보기
38. Guo L.-Q. Bai Y. Xu B.-Z. Pan W. Li J.-X. Qiao L.-J. Effect of hydrogen on pitting susceptibility of 2507 duplex stainless steel Corros. Sci. 2013 70 140 144 10.1016/j.corsci.2013.01.022

상세보기
39. Stratmann M. Streckel H. On the atmospheric corrosion of metal which are covered with thin electrolyte layers-I. Verification of the experimental technique Corros. Sci. 1990 30 681 696 10.1016/0010-938X(90)90032-Z

상세보기
40. Stratmann M. Streckel H. In situ Möβbauer spectroscopic study of reactions within rust layers Corros. Sci. 1989 29 1329 1352 10.1016/0010-938X(89)90123-6

상세보기
41. Dong L.-J. Han E.-H. Peng Q.-J. Ke W. Wang L. Environmentally assisted crack growth in 308L stainless steel weld metal in simulated primary water Corros. Sci. 2017 117 1 10 10.1016/j.corsci.2016.12.011

상세보기
42. Ma C. Han E.-H. Peng Q.-J. Ke W. Effect of polishing process on corrosion behavior of 308L stainless steel in high temperature water Appl. Surf. Sci. 2018 442 423 436 10.1016/j.apsusc.2017.12.190

상세보기
43. Stoller R.E. Toloczko M.B. Was G.S. Certain A.G. Dwaraknath S. Garner F.A. On the use of SRIM for computing radiation damage exposure Nucl. Instrum. Methods Phys. Res. Sect. B 2013 310 75 80 10.1016/j.nimb.2013.05.008

상세보기
44. Mohammadi A. Hamidi S. Asadabad M.A. The use of the SRIM code for calculation of radiation damage induced by neutrons Nucl. Instrum. Methods Phys. Res. Sect. B 2017 412 19 27 10.1016/j.nimb.2017.08.036

상세보기
45. ASTM E521 Standard Practice for Neutron Radiation Damage Simulation by Charged-Particle Irradiation Annual Book of ASTM Standards ASTM International West Conshohocken, PA, USA 2009
46. Örnek C. Engelberg D.L. SKPFM measured Volta potential correlated with strain localisation in microstructure to understand corrosion susceptibility of cold-rolled grade 2205 duplex stainless steel Corros. Sci. 2015 99 164 171 10.1016/j.corsci.2015.06.035

상세보기
47. Mechehoud F. Benaioun N.E. Hakiki N.E. Khelil A. Simon L. Bubendorff J.L. Thermally oxidized Inconel 600 and 690 nickel-based alloys characterizations by combination of global photoelectrochemistry and local near-field microscopy techniques (STM, STS, AFM, SKPFM) Appl. Surf. Sci. 2018 433 66 75 10.1016/j.apsusc.2017.10.094

상세보기
48. Guo L.-Q. Li M. Shi X.L. Yan Y. Li X.-Y. Qiao L.-J. Effect of annealing temperature on the corrosion behavior of duplex stainless steel studied by in situ techniques Corros. Sci. 2011 53 3733 3741 10.1016/j.corsci.2011.07.019

상세보기
49. Li W. Li D.-Y. Variations of work functions and corrosion behaviros of deformed copper surfaces Appl. Surf. Sci. 2005 240 388 395 10.1016/j.apsusc.2004.07.017

상세보기
50. Guo L.-Q. Zhao X.-M. Wang B.-C. Bai Y. Xu B.-Z. Qiao L.-J. The initial stage of atmospheric corrosion on interstitial free steel investigated by in situ SPM Corros. Sci. 2013 70 188 193 10.1016/j.corsci.2013.01.028

상세보기
51. Sathirachinda N. Pettersson R. Wessman S. Kivisäkk U. Pan J. Scanning Kelvin probe force microscopy study of chromium nitrides in 2507 super duplex stainless steel-Implications and limitations Electrochim. Acta. 2011 56 1792 1798 10.1016/j.electacta.2010.08.038

상세보기
52. Li M. Guo L.-Q. Qiao L.-J. Bai Y. The mechanism of hydrogen-induced pitting corrosion in duplex stainless steel studied by SKPFM Corros. Sci. 2012 60 76 81 10.1016/j.corsci.2012.04.010

상세보기
53. Egeland G.W. Valdez J.A. Maloy S.A. McClellan K.J. Sickafus K.E. Bond G.M. Heavy-ion irradiation defect accumulation in ZrN characterized by TEM, GIXRD, nanoindentation, and helium desorption J. Nucl. Mater. 2013 435 77 87 10.1016/j.jnucmat.2012.12.025

상세보기
54. Guo L.-Q. Lin M.-C. Qiao L.-J. Volinsky A.A. Ferrite and austenite phase identification in duplex stainless steel using SPM techniques Appl. Surf. Sci. 2013 287 499 501 10.1016/j.apsusc.2013.09.041

상세보기
55. Noonan J.R. Davis H.L. Atomic arrangements at metal surfaces Science. 1986 234 310 316 10.1126/science.234.4774.310 17834528

상세보기
56. Gao R. Cheng B. Zeng L.-F. Miao S. Hou J. Zhang T. Wang X.-P. Fang Q.-F. Liu C.-S. Microstructure, hardness and defect structure of the He irradiated ODS ferritic steel J. Alloys Compd. 2017 691 653 658 10.1016/j.jallcom.2016.08.312

상세보기
57. Gupta J. Hure J. Tanguy B. Laffont L. Lafont M.C. Andrien E. Characterization of ion irradiation effects on the microstructure, hardness, deformation and crack initiation behavior of austenitic stainless steel: Heavy ions vs protons J. Nucl. Mater. 2018 501 45 58 10.1016/j.jnucmat.2018.01.013

상세보기
58. Was G.S. Fundamentals of Radiation Materials Science: Metals and Alloys Springer New York, NY, USA 2017
59. Zinkle S.J. Matsukawa Y. Observation and analysis of defect cluster production and interactions with dislocations J. Nucl. Mater. 2004 329–333 88 96 10.1016/j.jnucmat.2004.04.298

상세보기
60. Victoria M. Baluc N. Bailat C. Dai Y. Luppo M.I. Schäublin R. Singh B.N. The microstructure and associated tensile properties of irradiated fcc and bcc metals J. Nucl. Mater. 2000 276 114 122 10.1016/S0022-3115(99)00203-2

상세보기
61. Lin X.-D. Peng Q.-J. Han E.-H. Ke W. Sun C. Jiao Z.-J. Irradiation-induced segregation at phase boundaries in austenitic stainless steel weld metal Scr. Mater. 2018 149 11 15 10.1016/j.scriptamat.2018.01.033

상세보기
62. Nakata K. Ikeda S. Hamada S. Hishinuma A. Microstructural development due to long-term aging and ion irradiation behavior in weld metals of austenitic stainless steel J. Nucl. Mater. 1996 233–237 192 196 10.1016/S0022-3115(96)00215-2

상세보기
63. Judge C.D. Bhakhri V. Jiao Z. Klassen R.J. Was G.S. Botton G.A. Griffiths M.J. The effects of proton irradiation on the microstructural and mechanical property evolution of inconel X-750 with high concentrations of helium J. Nucl. Mater. 2017 492 213 226 10.1016/j.jnucmat.2017.04.045

상세보기
64. Mente T. Boellinghaus T. Modeling of hydrogen distribution in a duplex stainless steel Weld. World. 2012 56 66 78 10.1007/BF03321397

상세보기

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Proton Irradiation Effects on Hardness and the Volta Potential of Welding 308L Duplex Stainless Steel 원문보기

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