研究生: |
吳柏毅 Wu, Po-Yi |
---|---|
論文名稱: |
高溫純水中過氧化氫於氧化鋯被覆304不□鋼表面之電化學行為分析 The Influence of ZrO2 Treatment on the Electrochemical Behavior of hydrogen peroxide on Type 304 Stainless Steels in High Temperature Water |
指導教授: |
蔡春鴻
Tsai, Chuen-Horng 葉宗洸 Yeh, Tsung-Kuang |
口試委員: | |
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: | 2008 |
畢業學年度: | 97 |
語文別: | 中文 |
論文頁數: | 135 |
中文關鍵詞: | 沸水式反應器 、沿晶應力腐蝕龜裂 、抑制性被覆 、氧化鋯 、電化學動態電位極化掃描 |
外文關鍵詞: | BWR, IGSCC, IPC, ZrO2, electrochemical potentiodynamic polarization |
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 |
摘要
沸水式反應器(Boiling Water Reactor, BWRs)長時間運轉,其內部隸屬壓力邊界(pressure boundary)的組件材料容易遭受沿晶應力腐蝕龜裂(Intergranular Stress Corrosion Cracking, IGSCC)劣化破壞。電化學腐蝕電位(electrochemical corrosion potential, ECP)為評估304不□鋼組件在288 ℃純水環境中是否發生沿晶應力腐蝕龜裂的重要指標。核能工業多採用加氫水化學( hydrogen chemistry, HWC )技術,降低組件材料的電化學腐蝕電位,防制IGSCC的發生。然而HWC在較高注氫量下(高於0.6ppm),會伴隨著輻射劑量率增加的副作用。另一種防蝕技術─抑制性被覆( Inhibitive Protective Coatings , IPC)的發展逐漸盛行。IPC技術甚至在不施行HWC情況下,亦能有效降低材料的腐蝕電位與腐蝕電流密度。
本研究利用IPC技術,針對模擬BWR不同管路位置水化學環境下預長氧化膜的304不□鋼試片施以氧化鋯被覆處理,在90 ℃條件下採用動態循環熱水沉積法( hydrothermal deposition),再對試片進行各種表面分析。並模擬BWR爐心因輻射水解(water radiolysis)而產生溶氧與過氧化氫的高溫高壓純水環境,隨氧化劑濃度變化進行電化學動態電位極化掃描(electrochemical potentiodynamic polarization)以了解不同水化學環境下預長氧化膜施行抑制性被覆前後電化學特性差異。
結果顯示,溶氧環境下預長氧化膜試片經由抑制性被覆後(O-90),SEM影像觀察到氧化鋯在試片表面呈局部較厚與較薄分佈。並由高溫極化掃描驗證了氧化鋯被覆對於溶氧有抑制的效果,能如預期的降低金屬的腐蝕電流密度、電化學腐蝕電位與氧化劑的交換電流密度,但是對低濃度的過氧化氫才有抑制效果。而過氧化氫環境下預長氧化膜試片施行抑制性被覆後(HP-90),被覆效果優於 O-90試片,且對於各種濃度的過氧化氫水環境皆有抑制成效,雖然不能有效降低金屬的腐蝕電位,卻能大幅削減其的腐蝕電流密度與過氧化氫的交換電流密度。
Abstract
As the boiling water reactors (BWRs) age, Intergranular stress corrosion cracking (IGSCC) of structural materials used in boiling water reactor (BWR) piping systems and vessel internals is the major degradation problem. Research has demonstrated that below a critical electrochemical corrosion potential (ECP) of -230 mVSHE, the susceptibility of stainless steel to IGSCC is substantially reduced. In past decade, several approaches to mitigating IGSCC by lowering the ECP have been developed and investigated. In the early 1980s, technique of hydrogen water chemistry (HWC), which reduced the oxidizing power of the BWR coolant environment by hydrogen injection and subsequently lowered the susceptibility of stainless steel components to SCC, was widely developed to mitigate the IGSCC problems. However, several side effects of HWC have been reported, such as increased N16 carry - over to the main stream line , a higher Co60 deposition rate , high H2 cost, etc. In addition, the IGSCC critical potential (-230 mVSHE) was difficult to achieve in highly oxidizing, high fluid flow and / or high level irradiation regions.
Recently, a new approach was explored to lower the corrosion potential and the corrosion current densities at all locations of BWRs, even without the presence of H2. It is termed Inhibitive Protective Coating (IPC), based on the assumption that a dielectric coating will inhibit the redox reaction on the surface and, therefore, the dissolution of metal at the crack-tip to which they are coupled – without the addition of hydrogen.
An experiment has been conducted to investigate the effects of inhibitive coating with zirconia (ZrO2) by hydrothermal deposition on Type 304 SS. The primary task in this study was to determine significant electrochemical parameters such as electrochemical corrosion potential, corrosion current density, exchange current density and Tafel constant of the reduction reactions of oxygen and hydrogen peroxide before and after inhibitive protective coatings. Specimens before and after the zirconia treating process were examined by the scanning electron microscopy (SEM) , the energy dispersive X-ray spectroscopy (EDX), focus ion beam image (FIB) and laser Raman spectra (LRS) . Effects of inhibitive coating with zirconia on Type 304 were measured by electrochemical potentiodynamic polarization tests in simulated BWR environment. Test results showed that treated SS specimens (O-90) in dissolved oxygen exhibited lower ECP than pre-oxidized specimens (P-O), and that specimen exhibited lower ECP only in lower hydrogen peroxide concentration. In high hydrogen peroxide concentration, the IPC treatment is unable to reduce ECP. On the contrary, the IPC specimens (HP-90) in dissolved H2O2 condition revealed nearly the same ECP level as that of the untreated ones (P-HP) for a wide H2O2 range. Furthermore, the corrosion current densities and exchanged current densities of H2O2 on the HP-90 specimens were lower apparently than those on the untreated ones. The overall results indicated that the ZrO2 treatment could effectively reduce the corrosion rate of Type 304 stainless steel in simulated BWR environments in views of both corrosion current densities and exchanged current densities.
參考文獻
[1] Fredric A. Simonen, Stephen R. Gosselin, “Life Prediction and Monitoring of Nuclear Power Plant Components for Service-Related Degradation” Journal of Pressure Vessel Technology, February 2001, Volume 123, Issue 1, pp. 58-64
[2] M. Shindo et al, Department of Materials Science and Engineering, Japan Atomic Energy Research Institute, “Effect of minor elements on irradiation assisted stress corrosion cracking of model austenitic stainless steels,” Journal of Nuclear Materials 233-237(1996)1393-1396.
[3] J.T. Busby, G.S. Was, E.A. Kenik , “Isolating the effect of radiation-induced segregation in irradiation-assisted stress corrosion cracking of austenitic stainless steels,” Journal of Nuclear Materials 302 (2002) 20–40
[4] M.A.Al-Anezi, G.S.Frankel and A.K. Agrawal, ”Susceptibility of Conventional Pressure Vessel Steel to Hydrogen-Induced Cracking and Stress-Oriented Hydrogen-Induced Cracking in Hydrogen Sulfide-Containing Diglycolamine Solutions,” Corrosion Vol.55 No.11 pp.1101-1109.
[5] Arsene S , Bai J.B. , Bompard P. , “Hydride Embrittlement and Irradiation Effects on the Hoop Mechanical Properties of Pressurized Water Reactor (PWR) and Boiling-Water Reactor (BWR) ZIRCALOY Cladding Tubes: Part I. Hydride Embrittlement in Stress-Relieved, Annealed, and Recrystallized ZIRCALOYs at 20 °C and 300 °C,” Metallurgical and Materials Transactions A, Volume34, Number 3, 1 March 2003, pp. 553-566.
[6] R. L. Cowan, Nuclear Engineering International, January 1986, p. 26.
[7] R. L. Cowan, “The Mitigation of IGSCC of BWR Internals with Hydrogen Water Chemistry,” Water Chemistry of Nuclear Reactor Systems 7 , BNES, Bournemouth England, Oct. 13-17 , 1996 , p. 196.
[8] Chien C. Lin, F. R. Smith, R. L. Cowan, “Effect of Hydrogen Water Chemistry on Radiation Field Buildup in BWRs, ” Nuclear Energy and Design 166 (1996) 31-36.
[9] U. S. Nuclear Regulatory Commission, Cracking of Vertical Welds in the Core Shroud and Degraded Repair, NRC Information Notice 97-17, April 4, 1997.
[10] P. L. Andresen, “Factors Governing The Predictoin of LWR Component SCC Behavior from Laboratory Data”, Corrosion /99, paper no. 145, Houston, TX, NACE International, (1999).
[11] P. L. Andresen, ”Emerging Issues and Fundamental Processes in Environmental Cracking in Hot Water, ” Corrosion Vol.64 No.5 pp.439-464.
[12] Materials Science and Engineering-An Introduction, 5th Edition W.D. Callister, Jr., John Wiley Sons, Inc., 1999
[13] P. Chung, “Quantitative Study of the Degree of Sensitization of Austenitic Steel by Electrochemical Measurements, ” M. S. Theses , the Ohio State Uni , 1979
[14] Herbert H. Uhlig & R. Winston Revie , Corrosion and Corrosion Control, Chapter 7.
[15] 王佰揚, “不同抑制性被覆條件之敏化304不□鋼在高溫純水環境中的電化學行為研究,” 國立清華大學碩士論文.
[16] P. Ford et al., “Development and Use of a Predictive Model of Crack Propagation in 304/316L, A533B/A508 and Inconel 600/182 Alloys in 288℃ Water”, Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 1988
[17] F. P. Ford et al., “Stress Corrosion Cracking of Low Alloy Steels under BWR Conditions; Assessment of CHR Algorithms”, 9th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors, 1999
[18] Thomas M. Angeliu, P. L. Andresen et al, “Applying Slip-Oxidation to the SCC of Austenitic Materials in BWR/PWR Environments”, CORROSION/98, paper No. 262, Houston, TX, NACE International, (1998).
[19] 鍾自強〝 焊接奧斯田鐵不锈鋼的問題及解決方法〞機械月刊,第七卷第十期,中華民國七十年10月號
[20] F.P. Ford , P.L. Andresen, “Corrosion in Nuclear Systems : Environment Assisted Cracking in Light Water Reactors,” in Corrosion Mechanisms , eds. P. Marcus. J. Ouder (New York, NY: Marcel Dekker , 1994 ). pp.501-546
[21] Kazushige ISHIDA et al., “Hydrazine and Hydrogen Co-injection to Mitigate Stress Corrosion Cracking of Structural Materials in Boiling Water Reactors, (II) Reactivity of Hydrazine with Oxidant in High Temperature Water under Gamma-irradiation”, Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol. 43, No. 3, p. 242–254 (2006)
[22] Kaesche, H., Die Korrosion der Metalle: Phys-Chem. Prinzipien une aktuelle Probleme, 3rd edn. Springer-Verlag, Berlin, 1990.
[23] Sato, N. and Okamoto, G. , Electrochemical Passivation of Metals, in Comprehensive Treatise of Electrochemistry, Vol. 4, Electrochemical Materials Science, ed. New York and London, 1981, pp. 193-245.
[24] McBee, C.L. and Kruger, J. Electrochim. Acta, 1972, 17, 1337-1341
[25] Winkler, R., Htittner, F. and Michel, F. VGB Kraftwerkstechnik, 1989, 69, 527-531.
[26] Winkler, R. and Lehmann, H. VGB Kraftwerkstechnik, 1985, 65,421426
[27] Asakura, Y. et al. Corrosion NACE, 1989, 45, 119-124.
[28] Y.J. Kim, “Analysis of Oxide Film Formed on Type 304 Stainless Steel in 288°C Water Containing Oxygen, Hydrogen, and Hydrogen Peroxide”, Corrosion Vol. 55, No.1, January 1999.
[29] Young-Jin Kim, “Effect of Water Chemistry on Corrosion Behavior of 304 SS in 288°C Water” International Water Chemistry Conference, San Francisco, October 2004.
[30] S. Uchida et al., “Effects of Hydrogen Peroxide on Intergranular Stress Corrosion Cracking of Stainless in High Temperature Water, (V) Characterization of Oxide Film on Stainless Steel by multilateral Surface Analyses,” Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.39, No.11, p.1199-1206(2002).
[31] S. Uchida et al., “Effects of Hydrogen Peroxide on Corrosion of Stainless Steel, (IV) Determination of Oxide Film Properties with Multilateral Surface Analyses ,” Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.42, No.2, p.233-241(2005).
[32] S. Uchida et al., “Effects of Hydrogen Peroxide on Corrosion of Stainless Steel, (V) Characterization of Oxide Film with Multilateral Surface Analyses,” Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.43, No.8, p.884-895(2006).
[33] B. Stellwag, “The Mechanism of Oxide Film Formation on Austenitic Stainless Steels in High Temperature Water,” Corrosion Science, Vol. 40, No. 2, p. 337 (1998).
[34] Lister, D.H., Davidson, R.D. and McAlpine, E. Corros. Sci., 1987, 27, 113-140.
[35] Leistikow, S. and Kraft, R. Werkstofjre und Korrosion, 1974,25, 12-25.
[36] Pick, M.E. and Segal, M.G. Nucl. Eng., 1983,22,433-444.
[37] Robertson, Corrosion Science, Vol.29, p.1275-1291, 1989.
[38] R. L. Cowan et al, GE Nuclear Energy, Vallecitos Nuclear Center, “Effects of hydrogen water chemistry on radiation field buildup in BWRs,” Nuclear Engineering and Design 166(1996)31-36.
[39] Y.F. Cheng, F.R. Steward, “Corrosion of carbon steels in high-temperature water studied by electrochemical techniques”, Corrosion Science 46 (2004) 2405–2420
[40] C.S. Kumai and T.M. Devine, “Oxidation of Iron in 288°C, Oxygen-Containing Water”, Corrosion Vol. 61, No. 3, 2005.
[41] D.F. Taylor, Corrosion 35 (1979): p. 550.
[42]B.Beverskog, “Pourbaix Diagrams for the Ternary System of Iron-Chromium-Nickel,” Corrosion Vol. 55, No.11, November 1999.
[43] Y.J. Kim, “In-Situ Electrochemical Impedance Measurement of Oxide Film on Type 304 Stainless Steel in High Temperature Water,” Corrosion Vol. 56, No.4, April 2000.
[44] S. Uchida et al., “Effects of Hydrogen Peroxide on Corrosion of Stainless Steel, (III) Evaluation of Electric Resistance of Oxide Film by Equivalent Circuit Analysis for Frequency Dependent Complex Impedances,” Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.42, No.1, p.66-74(2005).
[45] L. F. Lin, C. Y. Chao, and D. D. Macdonald, “ A Point Defect Model for Anodic Passive Films,” J. Electrochem. Soc, Vol.128, No.6,June 1981.
[46] D. D. Macdonald et al., "Theoretical Estimation of Crack Growth Rates in Type 304 Stainless Steel in BWR Coolant Environments," Corrosion, Vol. 52, p. 768-785 (1996).
[47] B. Stellwag, M. Lasch, and U. Staudt ,”Investigation into Alternatives to Hydrogen Water Chemistry in BWR Plants ," 1998 JAIF Conference, p186-193.
[48] R.L. Cowan, “The Mitigation of IGSCC of BWR Internals with Hydrogen Water Chemistry”, Nuclear Energy, 36, No.4, p.257, 1997.
[49] C. C. Lin, R.L. Cowan, “Effects of hydrogen water chemistry on radiation field buildup in BWRs”, Nuclear Energy and Design 166(1996)31-36
[50] Y.J. Kim, P. L. Andresen, ” Transformation Kinetics of Oxide Formed on Noble Metal-Treated Type 304 Stainless Steel in 288°C Water”, Corrosion, Vol. 59, No.6, p. 511-519 (2003).
[51] S. Hettiarachchi, R.J. Law, T.P. DiaZ, R.L. Cowan, “The First In-Plant Demonstration of Noble Metal Chemical Addition Technology for IGSCC Mitigation of BWR Internal,” 8th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors, August 1014, p.535(1997)
[52] Tsung-Kuang YEH , Digby 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, No.10, p.1228-1236(2006).
[53] R. Pathania, Zirconium Oxide Deposition to Mitigate IGSCC, BWRVIP Mitigation Committee Meeting, Atlanta, GA, October 1-3, 1997, EPRI.
[54] Dibyendu Ganguli and Debtosh Kundu, Central Glass and Ceramic Research Institute, India, “Preparation of amorphous ZrO2 coatings form metal-organic solutions,” Journal of Materials Science Letters, 3(1984)503-504.
[55] Y. J. Kim and P. L. Andresen, "Application of Insulated Protective Coatings for Reduction of Corrosion Potential in High Temperature Water," Corrosion, Vol. 54, No.12, p. 1012-1017 (1998).
[56] X. Zhou, I. Balachov and D. D. Macdonald, ”The Effect of Dielectric Coatings on IGSCC in Sensitized Type 304 SS in High Temperature Dilute Sodium Sulfate Solution, ”Corrosion Science. Vol.40 No.8 pp. 1349-1362.
[57] Z. F. Zhou, E. Chalkova, S. N. Lvov, P. Chou, R. Pathania , ”Development of a hydrothermal deposition for applying zirconia coationgs on BWR materials for IGSCC mitigation, ” Corrosion Science 49 (2007) 830-843.
[58] Tsung-Kuang YEH1, Ming-Yong LEE and Chuen-Horng 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, No.5, p.531-539(2002).
[59] Tsung-Kuang YEH, Chang-Tong LIU and Chuen-Horng TSAI, ” The Influence of ZrO2 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, No.9, p.805-815(2005).
[60] Tsung-Kuang YEH, Chuen-Horng TSAI and Yu-Hsiang 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, No.5, p.462-469(2005).
[61] Tsung-Kuang Yeh, Yuan-Chin Chien, Bai-Young Wang, Chuen-Horng Tsai, ” Electrochemical Characteristics of Zirconium Oxide Treated Type 304 Stainless
Steels of Different Surface Oxide Structures in High Temperature Water,” Corrosion Science (2008)
[62] M. Atik and M. A. Aegerter, “Corrosion resistant sol-gel ZrO2 coatings on stainless steel,” Journal of Non-Crystalline Solids 147&148(1992)813-819.
[63] Z. F. Zhou et al, “ Optimization of Zirconium Oxide Coating Technology to Mitigate IGSCC in BWRs,” Final Report , BWRVIP-109, EPRI , November, 2002.
[64] B. Stellwag and R. Kilian, Siemens Nuclear Power GmbH U.Staudt, VGB Germany “Investigation into Alternatives to Hydrogen Water Chemistry in BWR Plants,” 3rd Workshop on LWR Coolant Water Radiolysis and Electrochemistry.
[65] Z. F. Zhou et al, “Development of a hydrothermal deposition process for applying zirconia coatings on BWR materials for IGSCC mitigation,” Corrosion Science 49(2007)830-843
[66]Robert J. Hunter, “Zeta Potential in Collode - Science Principles and Applications,” Academic Press 1986.
[67] P. Jayaweeraa, S. Hettiarachchi,“Determination of the high temperature zeta potential and pH of zero charge of some transition metal oxides”Colloids trnd Swfaces A: Physicochemical and Engineering Aspects, 85 (1994) 19-27
[68] S. Uchida et al., “Effects of Hydrogen Peroxide on Corrosion of Stainless Steel,
(VI) Effects of Hydrogen Peroxide and Oxygen on Anodic Polarization
Properties of Stainless Steel in High Temperature Pure Water,” Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.44, No.5, p.758-766(2007).
[69] D. D. Macdonald, "Viability of Hydrogen Water Chemistry for Protecting In-Vessel Components of Boiling Water Reactors," Corrosion, Vol. 48, No. 3 p.194-205 (1992).
[70] 簡源進, “氧化鋯被覆與不同304不□鋼氧化膜對於溶氫與溶氧在模擬沸水式反應器環境中的電化學特性影響研究,” 國立清華大學碩士論文.
[71] W.L.Clarke, R. L. Cowan, W. L. Walker, “ Comparative Method for Measuring Degree of Sensitization in Stainless steel,” Intergranular Corrosion of Stainless Alloys, ASTM STP656, (1978)
[72] Azar P et al., “The Double Reactivation Method for Dectecting Sensitization in AISI 304 Stainless Steels,” Corrosion, Vol. 40, No. 11 p.584-594 (1984).
[73] R. Katsura et al., “DL-EPR Study of Neutron Irradiation in Type 304 Stainless Steel,” Corrosion, Vol.48, No.5, (1992)
[74] Yoichi Wada et al., “Effects of Hydrogen Peroxide on Intergranular Stress Corrosion Cracking of Stainless Steel in High Temperature Water, (IV) Effects of Oxide Film on Electrochemical Corrosion Potential,” Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.38, No.3, p.183-192(2001).
[75] S. Uchida et al., “Effects of Hydrogen Peroxide on Corrosion of Stainless Steel, (II) Evaluation of Oxide Film Properties by Complex Impedance Measurement,” Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.41, No.9, p.880-889(2004).
[76] S. Uchida et al., “Effects of Hydrogen Peroxide on Intergranular Stress Corrosion Cracking of Stainless Steel in High Temperature Water, (I) Effects of Hydrogen Peroxide on Electrochemical Corrosion Potential of Stainless Steel,” Journal of NUCLEAR SCIENCE and TECHNOLOGY, Vol.35, No.4, p.301-308(1998).
[77] 余佳銘, “不同加鋅水處理條件之304不□鋼在模擬沸水式反應器環境中的 電化學特性影響研究,” 國立清華大學碩士論文.