請用此 Handle URI 來引用此文件:
http://tdr.lib.ntu.edu.tw/jspui/handle/123456789/94703完整後設資料紀錄
| DC 欄位 | 值 | 語言 |
|---|---|---|
| dc.contributor.advisor | 薛人愷 | zh_TW |
| dc.contributor.advisor | Ren-Kae Shiue | en |
| dc.contributor.author | 陳泰丞 | zh_TW |
| dc.contributor.author | Tai-Cheng Chen | en |
| dc.date.accessioned | 2024-08-16T17:37:07Z | - |
| dc.date.available | 2024-08-17 | - |
| dc.date.copyright | 2024-08-16 | - |
| dc.date.issued | 2024 | - |
| dc.date.submitted | 2024-08-09 | - |
| dc.identifier.citation | References
[1] K.H. Lo, C.H. Shek, J.K.L. Lai, Recent developments in stainless steels, Materials Science and Engineering: R: Reports 65(4) (2009) 39-104. [2] S.J. Zinkle, G.S. Was, Materials challenges in nuclear energy, Acta Materialia 61(3) (2013) 735-758. [3] H.M. Chung, Aging and life prediction of cast duplex stainless steel components, International Journal of Pressure Vessels and Piping 50(1) (1992) 179-213. [4] M.D. Mathew, L.M. Lietzan, K.L. Murty, V.N. Shah, Low temperature aging embrittlement of CF-8 stainless steel, Materials Science and Engineering: A 269(1) (1999) 186-196. [5] J.S. Cheon, I.S. Kim, Evaluation of thermal aging embrittlement in CF8 duplex stainless steel by small punch test, Journal of Nuclear Materials 278(1) (2000) 96-103. [6] J.K. Sahu, U. Krupp, R.N. Ghosh, H.J. Christ, Effect of 475°C embrittlement on the mechanical properties of duplex stainless steel, Materials Science and Engineering: A 508(1) (2009) 1-14. [7] T.G. Lach, A. Devaraj, K.J. Leonard, T.S. Byun, Co-dependent microstructural evolution pathways in metastable δ-ferrite in cast austenitic stainless steels during thermal aging, Journal of Nuclear Materials 510 (2018) 382-395. [8] H.D. Solomon, T.M. Devine, A.S.f. Metals, Duplex Stainless Steels: A Tale of Two Phases, American Society for Metals1982. [9] S.R. Keown, R.G. Thomas, Role of delta ferrite in thermal aging of type 316 weld metals, Metal Science 15(9) (1981) 386-392. [10] A.A. Tavassoli, A. Bisson, P. Soulat, Ferrite decomposition in austenitic stainless steel weld metals, Metal Science 18(7) (1984) 345-350. [11] S. Kawaguchi, N. Sakamoto, G. Takano, F. Matsuda, Y. Kikuchi, L.u. Mráz, Microstructural changes and fracture behavior of CF8M duplex stainless steels after long-term aging, Nuclear Engineering and Design 174(3) (1997) 273-285. [12] G.E. Hale, S.J. Garwood, Effect of aging on fracture behaviour of cast stainless steel and weldments, Materials Science and Technology 6(3) (1990) 230-236. [13] J.-d. Kwon, S.-w. Woo, Y.-s. Lee, J.-c. Park, Y.-w. Park, Effects of thermal aging on the low cycle fatigue behavior of austenitic–ferritic duplex cast stainless steel, Nuclear Engineering and Design 206(1) (2001) 35-44. [14] S. Cicero, J. Setién, I. Gorrochategui, Assessment of thermal aging embrittlement in a cast stainless steel valve and its effect on the structural integrity, Nuclear Engineering and Design 239(1) (2009) 16-22. [15] J.J. Shiao, C.H. Tsai, J.J. Kai, J.H. Huang, Aging embrittlement and lattice image analysis in a Fe-Cr-Ni duplex stainless steel aged at 400°C, Journal of Nuclear Materials 217(3) (1994) 269-278. [16] S.J. Zinkle, J.T. Busby, Structural materials for fission & fusion energy, Materials Today 12(11) (2009) 12-19. [17] C. Pareige, S. Novy, S. Saillet, P. Pareige, Study of phase transformation and mechanical properties evolution of duplex stainless steels after long term thermal ageing (>20years), Journal of Nuclear Materials 411(1) (2011) 90-96. [18] D.A. Collins, E.L. Carter, T.G. Lach, T.S. Byun, A comprehensive study of the effects of long-term thermal aging on the fracture resistance of cast austenitic stainless steels, Nuclear Engineering and Technology 54(2) (2022) 709-731. [19] G. Obulan Subramanian, B.S. Kong, H.J. Lee, C. Jang, Evaluation of the thermal aging of δ-ferrite in austenitic stainless steel welds by electrochemical analysis, Scientific Reports 8(1) (2018) 15091. [20] P.H. Pumphrey, K.N. Akhurst, Aging kinetics of CF3 cast stainless steel in temperature range 300–400°C, Materials Science and Technology 6(3) (1990) 211-220. [21] O.K. Chopra, G. Ayrault, Aging degradation of cast stainless steel: Status and program, Nuclear Engineering and Design 86(1) (1985) 69-77. [22] S. Li, Y. Wang, S. Li, H. Zhang, F. Xue, X. Wang, Microstructures and mechanical properties of cast austenite stainless steels after long-term thermal aging at low temperature, Materials & Design 50 (2013) 886-892. [23] W. Yu, M. Fan, H. Gao, D. Yu, F. Xue, X. Chen, Effect of long-term aging on the fracture toughness of primary coolant piping material Z3CN20.09M, Nuclear Engineering and Design 327 (2018) 150-160. [24] H.M. Chung, T.R. Leax, Embrittlement of laboratory and reactor aged CF3,CF8, and CF8M duplex stainless steels, Materials Science and Technology 6(3) (1990) 249-262. [25] R. Fisher, E. Dulis, K. Carroll, Identification of the precipitate accompanying 885 F embrittlement in chromium steels, Trans. AIME 197(5) (1953) 690-695. [26] R. Williams, H. Paxton, The nature of aging of binary iron-chromium alloys around 500 C, J. Iron Steel Inst 185 (1957) 358-374. [27] G. Bonny, D. Terentyev, L. Malerba, New Contribution to the Thermodynamics of Fe-Cr Alloys as Base for Ferritic Steels, Journal of Phase Equilibria and Diffusion 31(5) (2010) 439-444. [28] M.K. Miller, I.M. Anderson, J. Bentley, K.F. Russell, Phase separation in the FeCrNi system, Applied Surface Science 94-95 (1996) 391-397. [29] K.L. Weng, H.R. Chen, J.R. Yang, The low-temperature aging embrittlement in a 2205 duplex stainless steel, Materials Science and Engineering: A 379(1) (2004) 119-132. [30] S.S. Brenner, M.K. Miller, W.A. Soffa, Spinodal decomposition of iron-32 at.% chromium at 470°C, Scripta Metallurgica 16(7) (1982) 831-836. [31] J.E. Brown, G.D.W. Smith, Atom probe studies of spinodal processes in duplex stainless steels and single- and dual-phase Fe-Cr-Ni alloys, Surface Science 246(1) (1991) 285-291. [32] F. Danoix, P. Auger, Atom Probe Studies of the Fe–Cr System and Stainless Steels Aged at Intermediate Temperature: A Review, Materials Characterization 44(1) (2000) 177-201. [33] P. Auger, F. Danoix, A. Menand, S. Bonnet, J. Bourgoin, M. Guttmann, Atom probe and transmission electron microscopy study of aging of cast duplex stainless steels, Materials Science and Technology 6(3) (1990) 301-313. [34] J.D. Tucker, M.K. Miller, G.A. Young, Assessment of thermal embrittlement in duplex stainless steels 2003 and 2205 for nuclear power applications, Acta Materialia 87 (2015) 15-24. [35] T. Hamaoka, A. Nomoto, K. Nishida, K. Dohi, N. Soneda, Effects of aging temperature on G-phase precipitation and ferrite-phase decomposition in duplex stainless steel, Philosophical Magazine 92(34) (2012) 4354-4375. [36] S.L. Li, Y.L. Wang, H.L. Zhang, S.X. Li, K. Zheng, F. Xue, X.T. Wang, Microstructure evolution and impact fracture behaviors of Z3CN20-09M stainless steels after long-term thermal aging, Journal of Nuclear Materials 433(1) (2013) 41-49. [37] A. Mateo, L. Llanes, M. Anglada, A. Redjaimia, G. Metauer, Characterization of the intermetallic G-phase in an AISI 329 duplex stainless steel, Journal of Materials Science 32(17) (1997) 4533-4540. [38] T.R. Leax, S.S. Brenner, J.A. Spitznagel, Atom probe examination of thermally ages CF8M cast stainless steel, Metallurgical Transactions A 23(10) (1992) 2725-2736. [39] S. Li, Y. Wang, X. Wang, F. Xue, G-phase precipitation in duplex stainless steels after long-term thermal aging: A high-resolution transmission electron microscopy study, Journal of Nuclear Materials 452(1) (2014) 382-388. [40] C. Pareige, J. Emo, S. Saillet, C. Domain, P. Pareige, Kinetics of G-phase precipitation and spinodal decomposition in very long aged ferrite of a Mo-free duplex stainless steel, Journal of Nuclear Materials 465 (2015) 383-389. [41] K. Chandra, V. Kain, V. Bhutani, V.S. Raja, R. Tewari, G.K. Dey, J.K. Chakravartty, Low temperature thermal aging of austenitic stainless steel welds: Kinetics and effects on mechanical properties, Materials Science and Engineering: A 534 (2012) 163-175. [42] F. Iacoviello, F. Casari, S. Gialanella, Effect of “475 °C embrittlement” on duplex stainless steels localized corrosion resistance, Corrosion Science 47(4) (2005) 909-922. [43] T. Yamada, S. Okano, H. Kuwano, Mechanical property and microstructural change by thermal aging of SCS14A cast duplex stainless steel, Journal of Nuclear Materials 350(1) (2006) 47-55. [44] S.L. Li, H.L. Zhang, Y.L. Wang, S.X. Li, K. Zheng, F. Xue, X.T. Wang, Annealing induced recovery of long-term thermal aging embrittlement in a duplex stainless steel, Materials Science and Engineering: A 564 (2013) 85-91. [45] C.-L. Lai, W.-F. Lu, J.-Y. Huang, Effect of δ-Ferrite Content on the Stress Corrosion Cracking Behavior of Cast Austenitic Stainless Steel in High-Temperature Water Environment, Corrosion 70(6) (2014) 591-597. [46] T.-C. Chen, J.-Y. Huang, R.-K. Shiue, L.-W. Tsay, Effects of heat treatments on the microstructure and environment-induced cracking of CF8A steel in simulated BWR water, International Journal of Pressure Vessels and Piping 191 (2021) 104382. [47] Y.H. Yao, J.F. Wei, Z.P. Wang, Effect of long-term thermal aging on the mechanical properties of casting duplex stainless steels, Materials Science and Engineering: A 551 (2012) 116-121. [48] K. Chandra, R. Singhal, V. Kain, V.S. Raja, Low temperature embrittlement of duplex stainless steel: Correlation between mechanical and electrochemical behavior, Materials Science and Engineering: A 527(16) (2010) 3904-3912. [49] S. Lee, P.T. Kuo, K. Wichman, O. Chopra, Flaw evaluation of theramally aged cast stainless steel in light-water reactor applications, International Journal of Pressure Vessels and Piping 72(1) (1997) 37-44. [50] W.-F. Lu, J.-Y. Huang, T.-Y. Yung, T.-C. Chen, K.-C. Tsai, Effects of thermal aging on the stress corrosion cracking behavior of cast stainless steel with different δ-ferrite levels in high temperature water environment, Journal of Nuclear Materials 568 (2022) 153900. [51] S. Jayet-Gendrot, P. Gilles, C. Migné, Behavior of duplex stainless steel casting defects under mechanical loadings, Nuclear Engineering and Design 197(1) (2000) 141-153. [52] P. Haušild, C. Berdin, P. Bompard, N. Verdière, Ductile fracture of duplex stainless steel with casting defects, International Journal of Pressure Vessels and Piping 78(9) (2001) 607-616. | - |
| dc.identifier.uri | http://tdr.lib.ntu.edu.tw/jspui/handle/123456789/94703 | - |
| dc.description.abstract | 本研究探討CF8A鑄造沃斯田鐵系不銹鋼,在高溫水環境下的應力腐蝕龜裂敏感性。研究中針對δ-肥粒鐵的含量、熱時效的時間以及軋延的程度對CF8A不銹鋼應力腐蝕龜裂敏感性影響,進行了詳細且全面的研究,並提出了應力腐蝕龜裂的機制。研究的結果表示,熱時效對CF8A不銹鋼的顯微組織影響較小,而軋延則會導致滑移線和αʹ-麻田散鐵在沃斯田鐵基體中形成。熱時效會增加δ-肥粒鐵的硬度,但對沃斯田鐵硬度的影響則較小。軋延會使δ-肥粒鐵和沃斯田鐵的硬度提升,且隨著軋延程度的增加,δ-肥粒鐵和沃斯田鐵的硬度也會隨之提升。材料的δ-肥粒鐵含量、熱時效時間及軋延程度的增加,均會顯著提高材料的最大抗拉強度,並降低材料的延展性。此外,越長的熱時效時間及越大的軋延程度,均會導致CF8A不銹鋼有更高的應力腐蝕龜裂敏感性。值得注意的是,高δ-肥粒鐵含量試樣的應力腐蝕龜裂敏感性較容易受熱時效影響,而低δ-肥粒鐵含量試樣的應力腐蝕龜裂敏感性則較容易受軋延影響。對於經過熱時效和軋延的低δ-肥粒鐵含量試樣,裂紋傾向沿滑移線擴展,從而使穿晶應力腐蝕成為主要的應力腐蝕龜裂機制;而對於經過熱時效和軋延的高δ-肥粒鐵含量試樣,裂紋則傾向沿δ-肥粒鐵與沃斯田鐵之間的相介面擴展,表示相介面的破裂為主要的應力腐蝕龜裂機制。 | zh_TW |
| dc.description.abstract | This study evaluated the stress corrosion cracking (SCC) susceptibility of CF8A cast austenitic stainless steels (CASS) in a high-temperature water environment. The combined effects of δ-ferrite content, thermal aging duration, and rolling degree on the SCC susceptibility of CF8A stainless steels were thoroughly examined, and the corresponding SCC mechanisms were proposed. The results showed that thermal aging has minimal impact on the microstructure of CF8A stainless steels, while rolling promotes the formation of slip lines and αʹ-martensite within the austenite matrix. Prolonged thermal aging increases the hardness of δ-ferrite but has little effect on the hardness of austenite. Rolling hardens both δ-ferrite and austenite, with hardness increasing as the degree of rolling increases. Increases in δ-ferrite content, thermal aging time, and rolling degree all lead to a significant rise in ultimate tensile strength (UTS) and a reduction in elongation of CF8A stainless steels. Additionally, longer thermal aging times and greater rolling degrees contribute to higher SCC susceptibility. Notably, the SCC susceptibility of specimens with higher δ-ferrite content is more affected by thermal aging, while those with lower δ-ferrite content are more influenced by rolling. For thermally-aged + rolled specimens with lower δ-ferrite content, cracks are more likely to propagate along slip lines, making transgranular stress corrosion cracking (TGSCC) the dominant SCC mechanism. For thermally-aged + rolled specimens with higher δ-ferrite content, cracks tend to propagate along the δ-ferrite/austenite interface, indicating that interface cracking is the predominant SCC mechanism. | en |
| dc.description.provenance | Submitted by admin ntu (admin@lib.ntu.edu.tw) on 2024-08-16T17:37:07Z No. of bitstreams: 0 | en |
| dc.description.provenance | Made available in DSpace on 2024-08-16T17:37:07Z (GMT). No. of bitstreams: 0 | en |
| dc.description.tableofcontents | Table of Contents
口試委員會審定書 i 學位論文學術倫理暨原創性聲明書 ii Acknowledgement iii 摘要 iv Abstract v Table of Contents vi List of Figures viii List of Tables xiii List of Abbreviations xiv Chapter 1 Introduction 1 Chapter 2 Literature Review 3 2-1 Introduction to cast austenitic stainless steels 3 2-2 Mechanism of thermal aging embrittlement 8 2-2-1 Spinodal decomposition 8 2-2-2 Precipitation of G-phase 19 2-2-3 Other microstructural evolutions 27 2-3 Effect of thermal aging on the mechanical properties 28 2-4 Effect of thermal aging on the corrosion behaviors 34 Chapter 3 Experimental Approach 37 3-1 Materials 37 3-2 Preparation of metallographic specimens 46 3-3 Mechanical tests 48 3-4 SCC tests 54 3-5 Microstructural analysis 59 3-6 Nomenclature 63 Chapter 4 Results 65 4-1 Microstructure 65 4-1-1 Solution annealed and thermally-aged specimens 65 4-1-2 Thermally-aged + rolled specimens 67 4-2 Hardness 71 4-2-1 Solution annealed and thermally-aged specimens 71 4-2-2 Thermally-aged + rolled specimens 75 4-3 Fatigue properties 78 4-4 Tensile properties in high temperature air 80 4-4-1 Solution annealed and thermally-aged specimens 80 4-4-2 Thermally-aged + rolled specimens 84 4-5 Tensile properties in high temperature water (SCC test) 89 4-5-1 Solution annealed and thermally-aged specimens 89 4-5-2 Thermally-aged + rolled specimens 93 4-5-3 The effect of high temperature water on UTS 98 4-5-4 The effect of high temperature water on elongation 102 4-6 Fracture surface analysis 106 4-6-1 Macroscopic analysis 106 4-6-2 Microscopic analysis 116 4-7 Cross-sectional analysis 119 4-7-1 Phase analysis 119 4-7-2 Plastic strain analysis 122 Chapter 5 Discussion 125 Chapter 6 Conclusions 131 Chapter 7 Future Work 133 References 135 Author’s Biography 141 List of Publication 142 | - |
| dc.language.iso | en | - |
| dc.subject | CF8A | zh_TW |
| dc.subject | 鑄造沃斯田鐵系不銹鋼 | zh_TW |
| dc.subject | 熱時效 | zh_TW |
| dc.subject | 軋延 | zh_TW |
| dc.subject | 應力腐蝕龜裂 | zh_TW |
| dc.subject | δ-肥粒鐵 | zh_TW |
| dc.subject | thermal aging | en |
| dc.subject | CF8A | en |
| dc.subject | δ-ferrite | en |
| dc.subject | stress corrosion cracking | en |
| dc.subject | rolling | en |
| dc.subject | cast austenitic stainless steel | en |
| dc.title | 熱時效鑄造沃斯田鐵系不銹鋼於模擬核能電廠冷卻水環境中之應力腐蝕龜裂敏感性研究 | zh_TW |
| dc.title | Study on the Stress Corrosion Cracking Susceptibility of Thermally-Aged Cast Austenitic Stainless Steels in Simulated Cooling Water Environments of Nuclear Power Plants | en |
| dc.type | Thesis | - |
| dc.date.schoolyear | 112-2 | - |
| dc.description.degree | 博士 | - |
| dc.contributor.oralexamcommittee | 郭東昊;蔡履文;葉宗洸;陳文祥 | zh_TW |
| dc.contributor.oralexamcommittee | Dong-Hau Kuo;Leu-Wen Tsay;Tsung-Kuang Yeh;Wen-Shiang Chen | en |
| dc.subject.keyword | CF8A,鑄造沃斯田鐵系不銹鋼,熱時效,軋延,應力腐蝕龜裂,δ-肥粒鐵, | zh_TW |
| dc.subject.keyword | CF8A,cast austenitic stainless steel,thermal aging,rolling,stress corrosion cracking,δ-ferrite, | en |
| dc.relation.page | 154 | - |
| dc.identifier.doi | 10.6342/NTU202404169 | - |
| dc.rights.note | 未授權 | - |
| dc.date.accepted | 2024-08-12 | - |
| dc.contributor.author-college | 工學院 | - |
| dc.contributor.author-dept | 材料科學與工程學系 | - |
| 顯示於系所單位: | 材料科學與工程學系 | |
文件中的檔案:
| 檔案 | 大小 | 格式 | |
|---|---|---|---|
| ntu-112-2.pdf 未授權公開取用 | 12.16 MB | Adobe PDF |
系統中的文件,除了特別指名其著作權條款之外,均受到著作權保護,並且保留所有的權利。
