04L不銹鋼和316L不銹鋼對於應力腐蝕龜裂(Stress Corrosion Cracking, SCC)有較高的敏感性，為了確保沸水式反應器(Boiling Water Reactor, BWR)結構組件的完整性，目前已有相當多的電廠採用了加氫水化學(Hydrogen Water Chemistry, HWC)技術。利用降低腐蝕電位(Electrochemical Corrosion Potential, ECP)來達到腐蝕抑制的效果。然而由於技術運轉規範的限制，台灣現行的核電廠設計在功率達到90%後才啟動加氫系統，考量到反應爐起動時特殊的水化學狀態，在此運轉條件下材料的腐蝕狀況值得加以重視和研究。
本研究採用慢應變速率拉伸實驗(Slow Strain Rate Test, SSRT)探討兩種低碳不鏽鋼在不同熱處理後，於一般水環境 (Normal Water Chemistry, NWC) 以及加氫水化學等兩種水化學環境下的應力腐蝕龜裂行為。試棒為棒狀圓柱，主要實驗溫度為288℃、250oC和200oC，拉伸速率為3.0 × 10-7 /s。接著以掃描式電子顯微鏡(Scanning Electron Microscopy, SEM)分析斷裂面型態以及表面樣貌。結果顯示316L不銹鋼相較於304L不銹鋼有較好的抗沿晶腐蝕能力。同時，在一般水化學環境下，對兩種不銹鋼而言較低的溫度都有著較低的應力腐蝕龜裂敏感性，其中316L在150oC下和304L在200oC下都無應力腐蝕龜裂出現，然而在250oC和288oC的結果都有著傾向多重裂縫起始的破裂形貌，呈現了較嚴重的應力腐蝕龜裂特徵。而加氫水化學的採用對於敏化316L抵抗應力腐蝕龜裂劣化有良好的效果，然而對於304L其優化效果卻不如預期。推論由於加氫水化學環境上和材料本身以及熱處理的差異造成不同的結果。其中加氫水化學中的氫/氧莫耳比、不銹鋼中的鉬和鎳含量造成了304L不銹鋼對於穿晶應力腐蝕龜裂可能有著較高的敏感性。

Hydrogen water chemistry (HWC) was proposed and widely adopted in BWRs worldwide to mitigate the problem of SCC. However, the hydrogen injection can only be applied during normal plant operation due to some limits inherent in the original design. The pressure and temperature gradient during plant start-up could cause the tensile stress conditions. Regarding the water environment, the above factors may contribute to the initiation of SCC.
In this study, we compared the SCC behavior between two type of stainless steel with different heat treatments at various temperature in the NWC and HWC during start-up. The SCC behavior and high temperature tensile properties were investigated by performing slow strain rate tensile (SSRT) tests at a constant strain rate of 3.0 × 10-7/s mainly at 200°C, 250°C and 288°C. After SSRT tests, scanning electron microscopy (SEM) was conducted to characterise the fractured surface. Basically, these two materials in the NWC test conditions showed lower SCC susceptibility with the lower testing temperature. Specimens tested under 250oC, however, showed higher tendency toward multiple cracks initiations. On the other hand, the performance of sensitized 316L in the aspects of tensile properties and fractography was substantially improved after introducing the HWC. Nevertheless, the unexpected performances were found on sensitized 304L after injecting hydrogen into the system. The slight differences between materials, heat treatment and water chemistry in the testing conditions were considered as the mian causes of these results.

摘要 i
Abstract ii
誌謝 iii
目錄 iv
表目錄 vii
圖目錄 viii
第一章 前言 1
1.1 研究動機-沸水式反應器組件完整性的問題 1
1.1.1 沸水式反應器組件材料的使用 1
1.1.2 沸水式反應器組件材料面臨的挑戰 3
1.2 研究目標 5
第二章 文獻回顧 6
2.1 應力腐蝕龜裂 6
2.1.1 304L不銹鋼和316L不銹鋼 6
2.1.2 應力腐蝕龜裂的肇因 7
2.1.3 應力腐蝕龜裂的現象描述 9
2.1.4 核電廠中的應力腐蝕龜裂因素 11
2.1.5 沃斯田鐵系不銹鋼於高溫純水中之氧化層結構 18
2.1.6 應力腐蝕龜裂的機制 27
2.1.7 沃斯田鐵系不銹鋼的應力腐蝕龜裂破壞型態 42
2.2 應力腐蝕龜裂的防治技術-加氫水化學 49
2.2.1 加氫水化學的理論基礎 49
2.2.2 反應器起動時水化學評估 51
2.2.3 加氫水化學的實際效益 54
2.2.4 加氫水化學面臨的挑戰 61
2.2.5 氫對沃斯田鐵系不銹鋼在高溫純水中的影響 63
2.3 評估應力腐蝕龜裂的方法 67
2.3.1 慢應變速率拉伸試驗 67
2.3.2 溫度對應力腐蝕龜裂的影響 71
2.3.3 拉伸速率對應力腐蝕龜裂的影響 79
2.3.4 應力腐蝕龜裂破裂形貌之轉變 82
第三章 實驗設備及步驟 85
3.1 實驗設計及方法 85
3.2 試片前處理 88
3.3 慢應變速率拉伸試驗 89
3.4 沿晶腐蝕敏感性測試 92
3.4.1 草酸測試 92
3.4.2 雙環電化學再活化法 93
第四章 結果與討論 96
4.1 304L不銹鋼和316L不銹鋼的沿晶腐蝕敏感性 96
4.2 起動狀態下一般水化學環境中的慢應變速率拉伸結果 99
4.2.1 應力-應變曲線結果 99
4.2.2 破裂面SEM分析 103
4.3 起動狀態下加氫水化學環境中的慢應變速率拉伸結果 130
第五章 結論 153
第六章 未來工作 155
參考文獻 156

[1] 郭榮卿, 核能電廠材料劣化與對策研究：現況與規劃. 台灣: 楊義卿, 2006.
[2] G. R. M. Horn. et al, "Experience and assessment of stress corrosion cracking in L-grade stainless steel BWR internals," Nuclear Engineering and Design, pp. 313-325, 1997.
[3] P. L. Andresen, "Stress Corrosion Cracking of Current Structural Materials in Commercial Nuclear Power Plants," Corrosion, vol. 69, pp. 1024-1038, 2013.
[4] International Atomic Energy Agency, “Stress Corrosion Cracking In Light Water Reactor: Good Practices And Lessons Learned,” IAEA, Vienna, NUCLEAR ENERGY SERIES No. NP-T-3.13, 2011.
[5] U. Ehrnstén et al, “Intergranular Cracking of AISI 316NG Stainless Steel in BWR Environment,” ENVDG 2001, Nevada, USA, August 2001.
[6] Nuclear Regulatory Commission, “Investigation and Evaluation of Stress Corrosion Cracking in Piping of Light Water Reactor Plants,” NRC, Washington, DC, USA, 1979.
[7] International Atomic Energy Agency, “Assessment and Management of Ageing of Major Nuclear Power Plant Components Important to Safety :BWR Pressure Vessel Internals,” IAEA, Vienna, IAEA-TECDOC-1471,2005.
[8] General Electric, GE Services Information Letter (SIL) 572.
[9] General Electric, “Core Support Shroud Crack Indications,” Rapid Information Communication Services Information Letter(RICSIL) 054, October, 1990.
[10] General Electric, GE Rapid Information Communication Services Information Letter (RICSIL) 068 Revision 1, April, 1994.
[11] T. M. Angeliu, “Microstructure Characterization of L-Grade Stainless Steels Relative to the IGSCC in BWR Environments,” NACE International, Houston, Texas, January, 2001.
[12] Yuichi Okamura et al, “Latest SCC Issues of Core Shroud and Recirculation Piping in Japanese BWRs,” SmiRT 17, Prague, Czech Republic, August, 2003.
[13] C. L. Briant et al, “Sensitization of Austenitic Stainless Steels, I. Controlled Purity Alloys,” Corrosion, vol. 38, pp. 468-477, 1982.
[14] R. A. Mulfor et al, “Sensitization of Austenitic Stainless Steels, II. Commercial Purity Alloys,” Corrosion, vol. 39, pp. 132-143, 1983.
[15] American Society for Testing and Materials, “Standard Specification for Chromium and Chromium-Nickel Stainless Steel Plate, Sheet, and Strip for Pressure Vessels and for General Applications,” ASTM International, ASTM A240/A240M-16a, PA, 2016.
[16] Fumio Umemura. et al, “Evaluation of IGSCC Susceptibility of Austenitic Stainless Steels Using Electrochemical Reactivation Method,” IAEA, vol. 29, pp. 163-169, 1980.
[17] P. L. Andresen, "Emerging issues and fundamental processes in environmental cracking in hot water," Corrosion, vol. 64, pp. 439-464, 2008.
[18] Russell H. Jones, “Stress corrosion cracking,” ASM international, 1992.
[19] P. L. Andresen, "Factors Governing the Prediction of LWR Component SCC Behavior From Laboratory Data," Corrosion, 1999.
[20] 陳威羽, “高溫純水中316L不銹鋼與52合金異材銲件之應力腐蝕龜裂行為研究,” 碩士, 工程與系統科學系, 國立清華大學, 2012.
[21] 蔡承學, “304不銹鋼與82合金異材銲件在模擬沸水式反應器環境中應力腐蝕行為研究,” 碩士, 工程與系統科學系, 國立清華大學, 2013.
[22] Ayumi Abe and Nobuaki Nagata et al, “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.
[23] Takaku et al., Karyoku Genshiryoku Hatsuden(Thermal and Nuclear Power), 28, 1079 (1977) (in Japanese).
[24] Kikuchi et al., Boshoku Gijutsu(Corrosion Engineering), 32, 497 (1983) (in Japanese).
[25] Electric Power Research Institute, “BWR Water Chemistry Guidelines,” EPRI, 2004
[26] Rosskamp M et al, “VGB guideline for the water in nuclear power plants with light water reactors(BWR),” VGB PowerTech, vol. 38, pp. 73-79, 2007.
[27] R. L. Cowan. et al, “Optimizing Water Chemistry in US Boiling Water Reactors,” Proc of VGB Conference Power Plant Chemistry, Essen, Germany, October, 1994.
[28] T. K. Yeh, F. Chu, “An Improved Model for Assessing the Effectiveness of Hydrogen Water Chemistry in Boiling Water Reactors,” Nuclear Science and Engineering, vol. 139, pp. 221-233, 2001.
[29] A. Wahid et al, “Corrosion of Weldments,” ASM Handbook, vol. 6, 2006.
[30] M.G. Fontana, “Corrosion Engineering, 3rd ed,” McGraw-Hill Book Company, 1987.
[31] Y. J. Kim, “Analysis of Oxide Film Formed on Type 304 Stainless Steel in 288oC Water Containing Oxygen, Hydrogen, and Hydrogen Peroxide,” Corrosion, vol. 55, 1999.
[32] Y. J. Kim, “Effect of Water Chemistry on Corrosion Behavior of 304 SS in 288oC Water,” in International Water Chemistry Conference, San Francisco, 2004.
[33] J. Wambach et al, “Oxidation of stainless steel under dry and aqueous conditions: oxidation behavior and composition,” Wiley InterScience, vol. 34, 164-170, 2002.
[34] Y. J. Kim, “Characterization of the Oxide Film Formed on Type 316 Stainless Steel in 288oC Water in Cyclic Normal and Hydrogen Water Chemistries,” Corrosion, vol. 51, 1995.
[35] M. Bojinov et al, in Proceedings of Chimie 2002 International Conference Water Chemistry in Nuclear Reactor Systems. Operation Optimisation and New Developments, Avignon, France, 2002.
[36] P. Rodriguez et al, “On the stress corrosion cracking mechanisms of austenitic stainless steels,” Bull. Mater. Sci., vol. 17, No. 6, pp. 685-698, November, 1994.
[37] H. H. Uhlig, “Physical metallurgy of stress corrosion fracture,” InterScience, 1959.
[38] S. Lynch, “Mechanistic and fractographic aspects of stress corrosion cracking.” Corros Rev, 30, pp 63-104, 2012.
[39] 劉松柏, 材料強度破壞學, 成璟文化, 2000.
[40] H. L. Logan, “Film-rupture mechanism of stress corrosion,” Journal of Research of the National Bureau of Standards, vol. 48, pp. 99-105, 1952.
[41] R. B. Mears et al, “Symposium on Stress-Corrosion Cracking of Metals,” Am. Soc. Testing Meterials-Am. Inst Mining Engrs., pp 329, 1944.
[42] F. H. Keating, “Symposium on Internal Stresses in Metals and Alloys,” Inst. Metals, p.329, 1948.
[43] 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.
[44] K. Sieradzki and R. C. Newman, “Brittle behavior of ductile metals during stress-corrosion cracking,” Philosophical Magazine A, vol. 51, Issue. 1, pp. 95-132, 1985.
[45] S. P. Lynch, “Progression markings, striations, and crack-arrest markings on fracture surfaces,” Materials Science and Engineering: A, vol.468-470, pp. 74-80, November, 2007.
[46] A. J. Mcevily Jr. et al, Electrochem. Soc., Vol. 112, pp. 131-137, 1965.
[47] R. J. H. Wanhill, National Aerospace Laboratory, The Netherlands, Unpublished work.
[48] D. Mackdonald et al, “Theoretical estimation of crack growth rates in type 304 stainless steel in boiling-water reactor coolant environments,” Corrosion, vol. 52, pp. 768-785, 1996.
[49] Denny A. Jones, “A unified mechanism of stress corrosion and corrosion fatigue cracking,” Metallurgical Transactions A, vol. 16A, June, 1985.
[50] Y. Mukai et al, “Fractographic observation of stress corrosion cracking of AISI 304 stainless steel in boiling 42 percent Magnesium Chloride solution,” ASTM STP 645, pp. 164-175, 1977.
[51] R. Liu et al, “Studies of the orientations of fracture surfaces produced in austenitic stainless steels by stress-corrosion cracking and hydrogen embrittlement,” Metallurgical Transactions A, vol 11, issue 9, pp. 1563-1574, September, 1980.
[52] E. I. Meletis et al, “A review of the crystallography of stress corrosion cracking,” Corros. Sci., vol. 26, pp. 63-90, 1986.
[53] E. I. Meletis et al, “The crystallography of stress corrosion cracking in face centered cubic single crystals,” Corros. Sci., vol. 24, pp. 843-862, 1984.
[54] S. Jani et al, “A mechanistic study of transgranular stress corrosion cracking of Type 304 stainless steel,” Metallurgical Transactions A, vol. 22A, June, 1991.
[55] J. P. Hirth, “Effects of Hydrogen on the properties of Iron and steel,” Metallurgical Transactions A, vol. 11A, June, 1980.
[56] L. B. Pfeil, “The effect of occluded hydrogen on the tensile strength of iron,” Proc. Royal Society of London, A112, pp. 128-195, 1926.
[57] D. G. Westlake, “A generalized model for hydrogen embrittlement,” Trans ASM, vol. 62, pp. 1000-1006, 1969.
[58] J. K. Tien et al, “Hydrogen transport by dislocations,” Metallurgical Transactions A, vol. 7A, June, 1976.
[59] H. K. Birnbaum, “Mechanisms of hydrogen related fracture of metals,” in Hydrogen Effects on Materials Behavior, 1990.
[60] R. A. Oriani, “Hydrogen – The versatile embrittler,” Corrosion, vol. 43, pp. 390-397, 1987.
[61] W. W. Gerberich et al, “Hydrogen induced cracking mechanisms – Are there critical experiments?,” in Hydrogen Effects in Materials, A. W., 1996.
[62] R. P. Gangloff, “Hydrogen assisted cracking of high strength alloys,” in Comprehensive Structural Integrity, pp. 31-101, 2003.
[63] S. P. Lynch, “Mechanisms of liquid-metal embrittlement and stress-corrosion cracking in high-strength aluminium alloys and other materials,” in Mechanisms of Environment Sensitive Cracking of Materials, pp.. 201-212, 1977.
[64] M. L. Holzworth et al, “Hydrogen-induced phase transformations in Type 304L stainless steels,” Corrosion, vol. 24, April, 1968.
[65] A. E. Pontini et al, “X-ray diffraction measurement of the stacking fault energy reduction induced by hydrogen in an AISI 304 steel,” Scripta Mater, vol. 11, p. 1831-1837, 1997.
[66] J. D. Hermida et at, “Stacking fault energy decrease in austenitic stainless steels induced by hydrogen pairs formation,” Scripta Mater, vol. 39, pp. 1145-1149, 1998.
[67] P. R. Swann, “Dislocation substructure vs transgranular stress corrosion susceptibility of single phase alloys,” Corrosion, vol. 19, pp. 102-112, 1963.
[68] D. L. Douglass, “Ordering, stacking faults and stress corrosion cracking in austenitic alloys,” Corrosion, vol. 20, pp. 15-28, 1964.
[69] H. D. Solomon, “Transgranular, granulated, and intergranular stress corrosion cracking in AISI 304 SS,” National Association of Corrosion Engineers, vol. 40, September, 1984.
[70] Hiroshi. Takaku et al, “Effects of cyclic tensile loading on stress corrosion cracking susceptibility sensitized Type 304 stainless steel in 290 C high Purity water,” National Association of Corrosion Engineers, vol. 35, November, 1979.
[71] M. Akashi et al, “Stress Corrosion Cracking Susceptibility of Various Stainless Steels in Oxygenated High Temperature Water,” IHI Eng., Rev. 11, pp. 8-15, 1978.
[72] F. Umemura et al, “Evaluation of IGSCC Susceptibility of Austenitic Stainless Steels Using Electrochemical Reactivation Method,” Corrosion, vol. 29, pp. 163-169, 1980.
[73] N. Saito et al, “Variation of Slow Strain Rate Test Fracture Mode of Type 304L Stainless Steel in 288oC Water,” Corrosion, vol. 56, No. 1, pp. 57-69, 2000.
[74] P. L. Andresen, “Emerging Issues and Fundamental Processes in Environmental Cracking in Hot Water,” Corrosion, vol. 64, No. 5, pp. 439-464, 2008.
[75] M. König. et al, “Effect of Sulphate and Chloride on Environmentally Assisted Cracking of Alloy 182 and Type 304 Stainless Steel in Simulated BWR Environments,” Proc. Int. Conf. Water Chemistry of Nuclear Reactor Systems, San Francisco, October, 2004.
[76] T. K. Yeh and M. Y. Wang, “Water Chemistry in the Primary Coolant Circuit of a Boiling Water Reactor during Start-up Operation,” Nuclear Science and Engineering, vol. 173, pp. 163-171, 2013.
[77] Nuclear Regulatory Commission, “Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors,” Generic Letter 94-03, NRC, U.S., 1994.
[78] A. M. Brass et al, “Hydrogen uptake in 316L stainless steel: Consequences on the tensile properties,” Corrosion Science, vol. 48, pp. 3222-3242, 2006.
[79] Y. Kim et al, “Effects of hydrogen diffusion on the mechanical properties of austenite 316L steel at ambient temperature,” Materials Transactions, vol. 52, pp. 507-513, 2011.
[80] M. Martin et al, “Influence of machining-induced martensite on hydrogen-assisted fracture of AISI type 034 austenitic stainless steel,” International Journal of Hydrogen Energy, vol. 36, pp. 11195-11206, 2011.
[81] A. L. Medina-Almazán et al, “Effect of uncontrolled hydrogen injection on SCC susceptibility of 304L steel in high temperature water,” Proceedings of the ASME 2017 Pressure Vessels and Piping Conference, July 16-20, Waikoloa, Hawaii, USA, 2017.
[82] P. Maulik et al, “Hydrogen induced martensitic transformations in austenitic steels,” Scripta Metallurgica, vol. 9, pp. 17-22, 1975.
[83] P. Rozenak et al, “HVEM studies of the effects of hydrogen on the deformation and fracture of AISI type 316 austenitic stainless steel,” Acta metal. Mater. Vol. 38, pp. 2031-2040, 1990.
[84] H. K. Birnbaum et al, “Hydrogen-enhanced localized plasticity- a mechanism for hydrogen-related fracture,” Materials Science and Engineering , A176, pp. 191-202, 1994.
[85] Nuclear Regulatory Commission, “Cracking in the Lower Region of the Core Shroud in Boiling Water Reactors,” Information Notice 94-42, NRC, U.S., 1995.
[86] Nuclear Regulatory Commission, “Reactor Vessel Top Guide and Core Plate Cracking,” Information Notice 95-17, NRC, U.S., 1995.
[87] B. Stellwag. et al, “Investigation into Alternatives to Hydrogen Water Chemistry in BWR Plants,” JAIF Conference, pp. 186-193, 1998.
[88] S. Hettiarachchi Et al, “First Application of NobleChemTM to an Operating BWR,” Water Chemistry in Nuclear Power Plants, vol. 98, pp. 13-16, Kashiwazaki, Japan, October, 1998.
[89] American Society for Testing and Materials, ”Standard Test Methods for Tension Testing of Metallic Materials,” ASTM International, Designation:E8/E8M, West Conshohocken, USA, 1924.
[90] 黃冠儒, “高溫純水中82合金與304低碳不銹鋼異材銲件之應力腐蝕研究,” 碩士, 工程與系統科學系, 國立清華大學, 2007.
[91] American Society for Testing and Materials, ”Standard Practice for Slow Strain Rate Testing to Evaluate the Susceptibility of Metallic Materials to Environmentally Assisted Cracking,” ASTM International, Designation:G129-00, West Conshohocken, USA, 2013.
[92] M. Wnag. et al, “Irradiation-Assisted Stress Corrosion Cracking Behavior of Age Hardened Nickel Based Alloys 624Plus and 725 in Boiling Water Reactors Environment,” 17th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Ottawa, Canada, August 9-13, 2015.
[93] M. Wnag. et al, “Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments Part II: Stress Corrosion Cracking,” 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Oregon, USA, August 13-17, 2017.
[94] Thierry Couvant. et al, “A Simulation of IGSCC of Austenitic Stainless Steels Exposed to Primary Water,” 17th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Ottawa, Canada, August 9-13, 2015.
[95] P. L. Andresen, “Crack initiation in CERT tests on type 304 stainless steel in pure water,” Corrosion, vol. 38, pp. 53-59, 1982.
[96] W. L. Pearl. et al, “Oxygen Monitoring and Control in BWR Plants,” Presentation to American Nuclear Society, June, 1977.
[97] T. Haruna, “Analysis of Initiation and Propagation of Stress Corrosion Cracks in Sensitized Type 304 Stainless Steel in High – Temperature Water,” Corrosion, vol. 60, pp. 1105-1112.
[98] W. Ruther. et al, “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.
[99] F. P. Ford. et al, “The Effect of Oxygen Temperature Combinations on the Stress Corrosion Susceptibility of Sensitized Type 304 Stainless Steel in High Purity Water,” National Association of Corrosion Engineers, vol. 35, pp. 569-574, 1979.
[100] A. K. Agrawal. et al, “Stress Corrosion of Sensitized and Quench Annealed Type 304 Stainless Steel in High Purity Water,” Corrosion, pp. 178, 1978.
[101] E. L. White. et al, “Influence of Combined Environmental Effects on Stress Corrosion Cracking of Welded Stainless Steel Piping,” EPRI Contract RP 311-1, Quarterly Report, July-September, 1977.
[102] Electric Power Research Institute, “BWRVIP Vessel and Internals Project, Feasibility Evaluation of BWR Hydrogen Injection for ECP Reduction During Startup,” EPRI, Technical Report, BWRVIP-226, 2009.
[103] P. L. Andresen, “Modeling of water and material chemistry effects on crack tip chemistry and resulting crack growth kinetics,” in Proceedings of the Third International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, Traverse City, August 1987.
[104] 邱又文, “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,” 碩士, 工程與系統科學系, 國立清華大學, 2014.
[105] Zhanpeng Lu. et al, “Transient and steady state crack growth kinetics for stress corrosion cracking of a cold worked 316L stainless steel in oxygenated pure water at different temperatures,” Corrosion Science, vol. 50, pp. 561-575, 2008.
[106] Zhanpeng Lu. et al, “Effectls of Loading Mode and Temperature on Stress Corrosion Crack Growth Rates of a Cold-Worked Type 316L Stainless Steel in Oxygenated Pure Water,” Corrosion, vol. 63, pp. 1021-1032, 2007.
[107] A. Jenssen. et al, “Effects of temperature on crack growth rate in sensitized type 304 stainless steel in pure and sulfate bearing BWR environments,” in Proceedings of the 10th International Symposium Environmental Degradation Materials Nuclear Power Systems-Water Reactors, NACE, 2001.
[108] P. L. Andresen. et al, “Effect of Martensite and Hydrogen on SCC of Stainless Steels and Alloy 600,” Corrosion, NACE, Paper No.228, 2001
[109] N. Totsuka. et al, “Effect of strain rate on primary water stress corrosion cracking fracture mode and crack growth rate of nickel alloy and austenitic stainless steel,” Corrosion, vol. 61, pp. 219-229, 2005.
[110] M. E. Indig et al, “High temperature electrochemical studies of the stress corrosion stainless steel,” Corrosion, vol. 35, pp. 288-295, 1979.