$\require{mediawiki-texvc}$

연합인증

연합인증 가입 기관의 연구자들은 소속기관의 인증정보(ID와 암호)를 이용해 다른 대학, 연구기관, 서비스 공급자의 다양한 온라인 자원과 연구 데이터를 이용할 수 있습니다.

이는 여행자가 자국에서 발행 받은 여권으로 세계 각국을 자유롭게 여행할 수 있는 것과 같습니다.

연합인증으로 이용이 가능한 서비스는 NTIS, DataON, Edison, Kafe, Webinar 등이 있습니다.

한번의 인증절차만으로 연합인증 가입 서비스에 추가 로그인 없이 이용이 가능합니다.

다만, 연합인증을 위해서는 최초 1회만 인증 절차가 필요합니다. (회원이 아닐 경우 회원 가입이 필요합니다.)

연합인증 절차는 다음과 같습니다.

최초이용시에는
ScienceON에 로그인 → 연합인증 서비스 접속 → 로그인 (본인 확인 또는 회원가입) → 서비스 이용

그 이후에는
ScienceON 로그인 → 연합인증 서비스 접속 → 서비스 이용

연합인증을 활용하시면 KISTI가 제공하는 다양한 서비스를 편리하게 이용하실 수 있습니다.

[해외논문] Effect of thermal ageing on the corrosion behaviour of austenitic stainless steel welds in the simulated PWR primary water

Corrosion science, v.172, 2020년, pp.108730 -   

Chen, Junjie (Korea Advanced Institute of Science and Technology) ,  Jang, Changheui (Korea Advanced Institute of Science and Technology) ,  Kong, Byeon Seo (Korea Advanced Institute of Science and Technology) ,  Xiao, Qian (Korea Advanced Institute of Science and Technology) ,  Obulan Subramanian, Gokul (Korea Advanced Institute of Science and Technology) ,  Kim, Ho Sub (Defense Agency for Technology and Quality) ,  Shin, Ji Ho (Korea Advanced Institute of Science and Technology)

Abstract AI-Helper 아이콘AI-Helper

Abstract The corrosion behaviour of as-welded and thermally aged ER316L in simulated pressurised water reactor (PWR) primary water was studied. Significant spinodal decomposition without G-phase was observed after thermal ageing. Thermal ageing does not change the duplex oxide film formation mechan...

Keyword

참고문헌 (47)

  1. Fujii 1 2015 17th Int. Conf. Environ. Degrad. Mater. Nucl. Power Syst. - Water React., Canadian Nuclear Society APT measurement of stainless steel welds after long-term aging and irradiation 

  2. Bjurman 1 2015 17th Int. Conf. Environ. Degrad. Mater. Nucl. Power Syst., Canadian Nuclear Society Phase separation study of in service thermally aged cast stainless steel - atom probe tomography 

  3. J. Nondestruct. Eval. David 15 129 1996 10.1007/BF00732040 Embrittlement of austenitic stainless steel welds 

  4. Acta Metall. Mater. Vitek 39 503 1991 10.1016/0956-7151(91)90118-K Low temperature aging behavior of type 308 stainless steel weld metal 

  5. Mater. Sci. Eng. A Chandra 534 163 2012 10.1016/j.msea.2011.11.055 Low temperature thermal aging of austenitic stainless steel welds: kinetics and effects on mechanical properties 

  6. Int. J. Press. Vessel. Pip. Hong 167 32 2018 10.1016/j.ijpvp.2018.10.006 Evaluation of the thermal ageing of austenitic stainless steel welds with 10 % of δ-ferrites 

  7. Metall. Mater. Trans. A Singh 48 1064 2017 10.1007/s11661-016-3919-3 Aging degradation of austenitic stainless steel weld probed by electrochemical method and impact toughness evaluation 

  8. Metall. Mater. Trans. A Lucas 47 3956 2016 10.1007/s11661-016-3584-6 Effects of thermal aging on material properties, stress corrosion cracking, and fracture toughness of AISI 316L weld metal 

  9. Corros. Sci. Jinlong 104 144 2016 10.1016/j.corsci.2015.12.005 Influence of sensitization on microstructure and passive property of AISI 2205 duplex stainless steel 

  10. J. Electrochem. Soc. Örnek 164 C207 2017 10.1149/2.0311706jes Characterization of 475°C embrittlement of duplex stainless steel microstructure via scanning kelvin probe force microscopy and magnetic force microscopy 

  11. Corros. Sci. Park 44 2817 2002 10.1016/S0010-938X(02)00079-3 Effects of aging at 475 °C on corrosion properties of tungsten-containing duplex stainless steels 

  12. Corrosion Kim 64 645 2008 10.5006/1.3279925 Stress corrosion cracking crack growth behavior of type 316L stainless steel weld metals in boiling water reactor environments 

  13. J. Nucl. Mater. Li 469 262 2016 10.1016/j.jnucmat.2015.11.043 Effects of long-term thermal aging on the stress corrosion cracking behavior of cast austenitic stainless steels in simulated PWR primary water 

  14. Mater. Charact. Cao 138 195 2018 10.1016/j.matchar.2018.02.010 Effect of thermal aging on oxide film of stainless steel weld overlay cladding exposed to high temperature water 

  15. Sci. Rep. Obulan Subramanian 8 15091 2018 10.1038/s41598-018-33422-x Evaluation of the thermal aging of δ-ferrite in austenitic stainless steel welds by electrochemical analysis 

  16. 18th Int. Conf. Environ. Degrad. Mater. Nucl. Power Syst. - Water React. Scenini 793 2018 Oxidation and SCC initiation studies of type 304L SS in PWR primary water 

  17. Corros. Sci. Kim 151 97 2019 10.1016/j.corsci.2019.02.012 Effect of zinc on the environmentally-assisted fatigue behavior of 316 stainless steels in simulated PWR primary environment 

  18. Corros. Sci. Oh 100 158 2015 10.1016/j.corsci.2015.07.022 A Study on the localized corrosion and repassivation kinetics of Fe-20Cr- x Ni (x = 0-20 wt%) stainless steels via electrochemical analysis 

  19. Int. J. Electrochem. Sci. Kim 8 11847 2013 10.1016/S1452-3981(23)13227-5 Study on the passive film of type 316 stainless steel 

  20. Corros. Sci. Huang 52 3444 2010 10.1016/j.corsci.2010.06.016 Electrochemical properties and growth mechanism of passive films on Alloy 690 in high-temperature alkaline environments 

  21. Electrochim. Acta de Araújo Figueiredo 56 7871 2011 10.1016/j.electacta.2011.05.077 Electrochemical investigation of oxide films formed on nickel alloys 182, 600 and 52 in high temperature water 

  22. Mater. Des. Jang 56 517 2014 10.1016/j.matdes.2013.12.010 The effects of reversion heat treatment on the recovery of thermal aging embrittlement of CF8M cast stainless steels 

  23. Scr. Mater. Lee 155 32 2018 10.1016/j.scriptamat.2018.06.016 Evaluation of thermal aging of δ-ferrite in austenitic stainless steel weld using nanopillar compression test 

  24. Mater. Charact. Danoix 44 177 2000 10.1016/S1044-5803(99)00048-0 Atom probe studies of the Fe-Cr system and stainless steels aged at intermediate temperature 

  25. Mater. Sci. Technol. Auger 6 301 1990 10.1179/mst.1990.6.3.301 Atom probe and transmission electron microscopy study of aging of cast duplex stainless steels 

  26. Acta Mater. Tucker 87 15 2015 10.1016/j.actamat.2014.12.012 Assessment of thermal embrittlement in duplex stainless steels 2003 and 2205 for nuclear power applications 

  27. Corros. Sci. Sun 51 2840 2009 10.1016/j.corsci.2009.08.006 Effects of temperature on the oxide film properties of 304 stainless steel in high temperature lithium borate buffer solution 

  28. Acta Met. Sin. Li 47 797 2011 Stress corrosion cracking behavior of dissimilar metal weld A508/52M/316L in high temperature water environment 

  29. J. Nucl. Mater. Chen 489 137 2017 10.1016/j.jnucmat.2017.03.029 Characterization of interfacial reactions and oxide films on 316L stainless steel in various simulated PWR primary water environments 

  30. J. Nucl. Sci. Technol. Terachi 40 509 2003 10.1080/18811248.2003.9715385 Influence of dissolved hydrogen on structure of oxide film on alloy 600 formed in primary water of pressurized water reactors 

  31. Corros. Sci. Lim 108 125 2016 10.1016/j.corsci.2016.02.040 Intergranular oxidation of Ni-based Alloy 600 in a simulated PWR primary water environment 

  32. J. Phys. F Met. Phys. Rothman 10 383 1980 10.1088/0305-4608/10/3/009 Self-diffusion in austenitic Fe-Cr-Ni alloys 

  33. Corrosion Beverskog 55 1077 1999 10.5006/1.3283945 Pourbaix diagrams for the ternary system of iron-chromium-nickel 

  34. Corros. Sci. Beverskog 39 43 1997 10.1016/S0010-938X(97)89244-X Revised pourbaix diagrams for chromium at 25-300 °C 

  35. J. Nucl. Mater. Chen 517 179 2019 10.1016/j.jnucmat.2019.02.019 The corrosion behaviour of alloy 690 tube in simulated PWR secondary water with the effect of solid diffusing hydrogen 

  36. Corros. Sci. Robertson 32 443 1991 10.1016/0010-938X(91)90125-9 The mechanism of high temperature aqueous corrosion of stainless steels 

  37. Corros. Sci. Huang 52 3444 2010 10.1016/j.corsci.2010.06.016 Electrochemical properties and growth mechanism of passive films on Alloy 690 in high-temperature alkaline environments 

  38. Solid State Ion. Dieckmann 12 1 1984 10.1016/0167-2738(84)90126-7 Point defects and transport properties of binary and ternary oxides 

  39. Corros. Sci. Hirano 31 557 1990 10.1016/0010-938X(90)90162-X The relationship between the characteristics of oxide film and stress corrosion susceptibility of Ni-Cr-Fe alloy in high temperature water 

  40. Terachi 2016 Corros. 2006 Characterization of oxide film behaviors on 316 stainless steels in high temperature water - influence of hydrogen and oxygen considerations for initiation of SCC 

  41. Corrosion Olefjord 38 46 1982 10.5006/1.3577318 The composition of the surface during passivation of stainless steels 

  42. Appl. Surf. Sci. Guo 258 9087 2012 10.1016/j.apsusc.2012.06.003 Water adsorption behavior on metal surfaces and its influence on surface potential studied by in situ SPM 

  43. Sci. Rep. Guo 6 20660 2016 10.1038/srep20660 Electron work functions of ferrite and austenite phases in a duplex stainless steel and their adhesive forces with AFM silicon probe 

  44. Mater. Corros. You 69 1205 2018 10.1002/maco.201709984 Passive film properties of Z3CN20.09M duplex stainless steel aged for different times 

  45. J. Alloys Compd. Fattah-alhosseini 639 301 2015 10.1016/j.jallcom.2015.03.142 Comparison of electrochemical behavior between coarse-grained and fine-grained AISI 430 ferritic stainless steel by Mott-Schottky analysis and EIS measurements 

  46. J. Nucl. Mater. Yang 518 305 2019 10.1016/j.jnucmat.2019.03.016 The electrochemical properties of alloy 690 in simulated pressurized water reactor primary water: effect of temperature 

  47. Corros. Sci. Wei 146 44 2019 10.1016/j.corsci.2018.10.025 Effect of roughness on general corrosion and pitting of (FeCoCrNi)0.89(WC)0.11 high-entropy alloy composite in 3.5 wt.% NaCl solution 

LOADING...

활용도 분석정보

상세보기
다운로드
내보내기

활용도 Top5 논문

해당 논문의 주제분야에서 활용도가 높은 상위 5개 콘텐츠를 보여줍니다.
더보기 버튼을 클릭하시면 더 많은 관련자료를 살펴볼 수 있습니다.

관련 콘텐츠

유발과제정보 저작권 관리 안내
섹션별 컨텐츠 바로가기

AI-Helper ※ AI-Helper는 오픈소스 모델을 사용합니다.

AI-Helper 아이콘
AI-Helper
안녕하세요, AI-Helper입니다. 좌측 "선택된 텍스트"에서 텍스트를 선택하여 요약, 번역, 용어설명을 실행하세요.
※ AI-Helper는 부적절한 답변을 할 수 있습니다.

선택된 텍스트

맨위로