研究生: |
邱又文 |
---|---|
論文名稱: |
304不銹鋼於模擬沸水式反應器起動狀態之水化學環境中的應力腐蝕龜裂行為研究 Stress Corrosion Cracking of Type 304 Stainless Steels in Simulated Boiling Water Reactor Water Chemistry Environments under Start-up conditions |
指導教授: |
葉宗洸
王美雅 |
口試委員: |
歐陽汎怡
黃俊源 |
學位類別: |
碩士 Master |
系所名稱: |
原子科學院 - 工程與系統科學系 Department of Engineering and System Science |
論文出版年: | 2014 |
畢業學年度: | 103 |
語文別: | 中文 |
論文頁數: | 78 |
中文關鍵詞: | 應力腐蝕龜裂 、慢速拉伸試驗 、反應器啟動過程 |
相關次數: | 點閱:3 下載:0 |
分享至: |
查詢本校圖書館目錄 查詢臺灣博碩士論文知識加值系統 勘誤回報 |
本研究利用慢速拉伸試驗(Slow Strain Rate Tensile tests, SSRT)對304不鏽鋼在沸水式反應器起動過程之不同溫度下應力腐蝕龜裂敏感性(stress corrosion cracking susceptibility)進行測試。分別在四個試驗溫度150 °C、200 °C、250 °C和288 °C進行,包含一般水化學條件(Normal Water Chemistry, NWC)和加氫水化學(Hydrogen Water Chemistry, HWC),藉此探討304不鏽鋼應力腐蝕龜裂敏感性在一般水化學下之溫度效應以及加氫水化學之防蝕效益評估。
試驗結果顯示,在150 °C之低溫下,由於應力腐蝕龜裂之驅動力不足,一般水化學和加氫水化學之結果均無任何SCC出現。在一般水化學之不同溫度下,304不鏽鋼之應力腐蝕龜裂敏感性由高至低依序是250 °C、288 °C和200 °C,破斷面分析結果顯示在200 °C、250 °C下應力腐蝕龜裂之行為屬多重裂縫成長,而288 °C為單一裂縫成長,在250 °C下由於多重裂縫成長且發生了裂縫接合之現象,因此其應力腐蝕龜裂敏感性高於相對於更高溫之288 °C;而加氫水化學之結果顯示,在200 °C、250 °C或288 °C下之破斷面分析結果均未發現沿晶應力腐蝕龜裂之出現,各溫度之結果均顯示有較一般水化學環境下更多之二次裂口,但其應是頸縮區累積了大量應變所致,此結果並不影響加氫水化學對應力腐蝕龜裂之抑制效果。
[1] R. Cowan, Nuclear Engineering International, January 1986.
[2] M. Indig, "Recent Advances in Measuring ECPs in BWR Systems," 4th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, NACE, 1989.
[3] C. C. Lin, F. Smith, and R. Cowan, "Effects of hydrogen water chemistry on radiation field buildup in BWRs," Nuclear engineering and design, vol. 166, pp. 31-36, 1996.
[4] N. R. Commission, "Cracking of Vertical Welds in the Core Shroud and Degraded Repair," NRC Information Notice 97-17, April 4 1997.
[5] S. Sawochka, M. Leonard, J. Gianelli, A. Odell, and S. Garcia, "Effect of hydrazine, carbo-hydrazine and hydrogen injection on noble metal treated stainless steel ECP and IGSCC mitigation during BWR startup," INIS, vol. 42, 2011.
[6] T.-K. Yeh, C.-T. Liu, and C.-H. Tsai, "The Influence of ZrO 2 Treatment on the Electrochemical Behavior of Oxygen and Hydrogen on Type 304 Stainless Steels in High Temperature Water," Journal of Nuclear Science and Technology, vol. 42, pp. 809-815, 2005.
[7] T.-K. Yeh, C.-H. Tsai, and Y.-H. Cheng, "The influence of dissolved hydrogen on the corrosion of type 304 stainless steels treated with inhibitive chemicals in high temperature pure water," Journal of Nuclear Science and Technology, vol. 42, pp. 462-469, 2005.
[8] T.-K. Yeh, M.-Y. Lee, and C.-H. Tsai, "Intergranular stress corrosion cracking of type 304 stainless steels treated with inhibitive chemicals in simulated boiling water reactor environments," Journal of Nuclear Science and Technology, vol. 39, pp. 531-539, 2002.
[9] T.-K. Yeh and D. D. Macdonald, "The efficiency of noble metals in reducing the corrosion potential in the primary coolant circuits of boiling water reactors operating under hydrogen water chemistry operation," Journal of Nuclear Science and Technology, vol. 43, pp. 1228-1236, 2006.
[10] T.-K. Yeh and C.-H. Tsai, "Intergranular stress corrosion cracking of platinum treated type 304 stainless steels in high temperature water," Journal of nuclear science and technology, vol. 41, pp. 116-125, 2004.
[11] T.-K. Yeh, "Crack Growth of ZrO2 Treated Type 304 Stainless Steels in High Temperature Pure Water," Proceedings of International Conference on Water Chemistry of Nuclear Systems, San Francisco, Electric Power Research Institute, October 2004.
[12] T.-K. Yeh, C.-H. Tsai, and C.-Y. Chang, "Crack Growth Behavior of Platinum Treated Type 304 Stainless Steels in High Temperature Pure Water," Proceedings of the Symposium on Water Chemistry and Corrosion in Nuclear Power Plants in Asia 2003, November 2003.
[13] P. L. Andresen, "Stress corrosion cracking of current structural materials in commercial nuclear power plants," Corrosion, vol. 69, pp. 1024-1038, 2013.
[14] S. Venugopal, S. Mannan, and P. Rodriguez, "Optimum design of a hot extrusion process for AISI type 304L stainless steel using a model for the evolution of microstructure," Modelling and Simulation in Materials Science and Engineering, vol. 10, p. 253, 2002.
[15] H. Hong, B. Rho, and S. Nam, "A study on the crack initiation and growth from δ-ferrite/γ phase interface under continuous fatigue and creep-fatigue conditions in type 304L stainless steels," International journal of fatigue, vol. 24, pp. 1063-1070, 2002.
[16] P. L. Andresen, "Factors Governing the Prediction of LWR Component SCC Behavior From Laboratory Data," Corrosion, 1999.
[17] P. L. Andresen, "Emerging issues and fundamental processes in environmental cracking in hot water," Corrosion, vol. 64, pp. 439-464, 2008.
[18] R. H. Jones, "Stress corrosion cracking," ASM international, 1992.
[19] H. H. Uhlig, "Physical metallurgy of stress corrosion fracture," interscience, 1959.
[20] 劉松柏, "材料強度破壞學," 成璟文化, 2000.
[21] H. H. Uhlig and R. W. Revie, "Corrosion and Corrosion Control, Chapter 7."
[22] N. Nielsen, "Observations and Thoughts on Stress Corrosion Mechanisms ASTM 1970 Gillett Memorial Lecture," Corrosion, vol. 27, pp. 173-189, 1971.
[23] 徐堅, "金屬的應力腐蝕斷裂(下)," 化工部設備設計技術中心站, 1980.
[24] J. Silcock and P. Swann, "Nucleation and growth of transgranular stress corrosion cracks in austenitic stainless steels," in Environment-Sensitive Fracture of Engineering Materials\ Proc. Conf.\, Chicago, Illinois, U. S. A., Oct. 1977, 1979, pp. 133-152.
[25] H. L. Logan, "Film-rupture mechanism of stress corrosion," Journal of Research of the National Bureau of Standards, vol. 48, pp. 99-105, 1952.
[26] F. Ford and P. Andresen, "Development and use of a predictive model of crack propagation in 304/316L, A533B/A508 and Inconel 600/182 alloys in 288 0 C water," in Proceedings of the third international symposium on environmental degradation of materials in nuclear power systems, 1988.
[27] D. Macdonald, P.-C. Lu, M. Urquidi-Macdonald, and T.-K. Yeh, "Theoretical estimation of crack growth rates in type 304 stainless steel in boiling-water reactor coolant environments," Corrosion, vol. 52, pp. 768-785, 1996.
[28] P. L. Andresen, "Crack initiation in CERT tests on type 304 stainless steel in pure water," Corrosion, vol. 38, pp. 53-59, 1982.
[29] W. Ruther, W. Soppet, and T. Kassner, "Effect of temperature and ionic impurities at very low concentrations on stress corrosion cracking of AISI 304 stainless steel," Corrosion, vol. 44, pp. 791-799, 1988.
[30] P. L. Andresen, "Effects of temperature on crack growth rate in sensitized type 304 stainless steel and alloy 600," Corrosion, vol. 49, pp. 714-725, 1993.
[31] M. Fox, A. Gianuzzi, and J. Danko, Mechanisms of environmental cracking in systems peculiar to the power generation industry: Electric Power Research Institute, 1982.
[32] P. L. Andresen, "Effects of temperature and corrosion potential on SCC," 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 2011.
[33] J. Stjärnsäter, A. Jenssen, C. Jansson, K. Gott, B. Forssgren, B. Bengtsson, et al., "The Effect of Temperature on the Crack Growth Rate of Stainless Steel and NI-Alloys in Simulated BWR Environment," 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 2011.
[34] "BWRVIP-226: BWR Vessel and Internals Project
Feasibility Evaluation of BWR Hydrogen Injection for ECP Reduction During Startup," 2009.
[35] A. Abe, H. Tobita, N. Nagata, K. Dozaki, and H. Takiguchi, "Mitigation of SCC initiation on BWR core internals by means of Hydrogen water chemistry during start-up," Nuclear science and engineering, vol. 149, pp. 312-324, 2005.
[36] K. Ishida, Y. Wada, M. Tachibana, N. Ota, and M. Aizawa, "Applying Hydrogen Water Chemistry to Boiling Water Reactor during Normal Operation and Start-up to Mitigate Stress Corrosion Cracking at Shimane Nuclear Power Station's Unit 2," International Conference on Water Chemistry of Nuclear Reactor Systems, 2008.
[37] E. Pugh, "Progress toward understanding the stress corrosion problem," Corrosion, vol. 41, pp. 517-526, 1985.
[38] J. H. Zheng and W. Bogaerts, "Effects of cold work on stress corrosion cracking of type 316L stainless steel in hot lithium hydroxide solution," Corrosion, vol. 49, pp. 585-593, 1993.
[39] K. Lian and E. Meletis, "Environment-induced deformation localization during transgranular stress corrosion cracking," Corrosion, vol. 52, pp. 347-355, 1996.
[40] B. Lichter, W. Flanagan, J.-S. Kim, J. Elkenbracht, and M. Van Hunen, "Mechanistic studies of stress corrosion cracking: application of the corrosion-assisted cleavage model to results using oriented single crystals," Corrosion, vol. 52, pp. 453-463, 1996.