RESEARCH TRENDS ON MICRO AND NANO--SCALE MATERIALS DEGRADATION IN NUCLEAR POWER PLANT

doi:10.3724/SP.J.1037.2011.00441

Acta Metall Sin

2011, Vol. 47

Issue (7): 769-776 DOI: 10.3724/SP.J.1037.2011.00441

论文

Current Issue | Archive | Adv Search

RESEARCH TRENDS ON MICRO AND NANO--SCALE MATERIALS DEGRADATION IN NUCLEAR POWER PLANT

HAN En--Hou

1) State Key Laboratory for Corrosion and Protection, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016
2) Liaoning Key Laboratory for Safety and Assessment Technique of Nuclear Materials, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016

Cite this article:

HAN En--Hou. RESEARCH TRENDS ON MICRO AND NANO--SCALE MATERIALS DEGRADATION IN NUCLEAR POWER PLANT. Acta Metall Sin, 2011, 47(7): 769-776.

Download:

PDF(2328KB)
Export: BibTeX | EndNote (RIS)

Abstract The recent research status of materials degradation in nuclear power plant (NPP) has been analyzed. The main research progresses include: kinetics of corrosion electrochemistry in high temperature pressurised water, preferential intergranular oxidation and the degradation of grain boundary strength, special grain boundary optimized materials corrosion resistance, tight crack of stress corrosion cracking, nano-scale atom cluster formation and effects. The research trends and key problems have been proposed, such as kinetics of corrosion electrochemistry in high temperature high pressure water, especially the effect of contaminating species on micro-process of corrosion; characterization of microstructure, physical, chemical and mechanical properties of surface film and near-surface materials, repassivation behavior of passive film, especially ion diffusion micro-process in the surface film and near-surface materials; the effects of as-received surface and water chemistry on crack incubation and initiation; application of materials degradation mechanisms. In order to characterize the material environmental behavior, it is important to control the research and environment condition, and to develop new test methods in simulated NPP environment.

Key words: key material in nuclear power plant stainless steel nickel--based alloy low alloy steel zirconium alloy corrosion stress corrosion cracking corrosion fatigue, flow assisted corrosion irradiation degradation

Received: 12 July 2011

Fund:

Supported by National Basic Research Program of China (No.2011CB610500) and National Science and Technology Major Project (No.2011ZX06004-009)

	Service

	E-mail this article
	Add to citation manager
	E-mail Alert
	RSS
	（）
	Articles by authors
	HAN En-Hou

URL:

https://www.ams.org.cn/EN/10.3724/SP.J.1037.2011.00441 OR https://www.ams.org.cn/EN/Y2011/V47/I7/769

[1] Macdonald D D, Scott A, Wentrcek P. J Electrochem Soc, 1979; 126: 1618

[2] Hettiarachchi S, Makela K, Song H, Macdonald D D. J Electrochem Soc, 1992; 139: L3

[3] Kriksunov L B, Macdonald D D, Millett P J. J Electrochem Soc, 1994; 141: 3002

[4] Kriksunov L B, Macdonald D D. J Electrochem Soc, 1998; 145: 4107

[5] Huang S, Daehling K, Carleso T E, Abdel-latif M, Taylor P,Wai C, Propp A. ACS Symp Ser, 1989; 406: 287

[6] Zhang L, Han E H, Ke W, Guan H. Chin Pat, ZL 02 1 32544.8, 2005

(张丽, 韩恩厚, 柯伟, 关辉. 中国专利, ZL 02 1 32544.8, 2005)

[7] Zhang L, Han E H, Ke W, Guan H. Chin Pat, ZL 02 2 74025.2, 2003

(张丽, 韩恩厚, 柯伟, 关辉. 中国实用新型专利, ZL 02 2 74025.2, 2003)

[8] Guan H, Zhang L, Han E H, Ke W. Chin Pat, ZL 02 2 74026.0, 2003

(关辉, 张丽, 韩恩厚, 柯伟. 中国实用新型专利, ZL 02 2 74026.0, 2003)

[9] Sun H, Wu X Q, Han E H. Chin Pat, CN101470093, 2009

(孙华, 吴欣强, 韩恩厚. 中国专利, CN101470093, 2009)

[10] Sun H, Wu X Q, Han E H. Chin Pat, CN101470094, 2009

(孙华, 吴欣强, 韩恩厚. 中国专利, CN101470094, 2009)

[11] Han E H, Wang J Q, Wu X Q, Ke W, Acta Metall Sin, 2010; 46: 1379

(韩恩厚, 王俭秋, 吴欣强, 柯伟, 金属学报, 2010; 46: 1379)

[12] Sun H, Wu X Q, Han E H. Corros Sci, 2009; 51: 2565

[13] Huang J B, Wu X Q, Han E H. Corros Sci, 2009; 51: 2976

[14] Sun H, Wu X Q, Han E H. Corros Sci, 2009; 51: 2840

[15] Kuang W J, Han E H, Wu X Q, Rao J C. Corros Sci, 2010; 52: 3654

[16] Huang J, Wu X Q, Han E H. Corros Sci, 2010; 52: 3444

[17] Asher R C, Davis D, Kirstein T B A, McCullen P A J, White J F. Corros Sci, 1970; 10: 695

[18] ChenXW, BaiXD, XueX Y. Rare Met Mater Eng, 2003; 32: 321

(陈小文, 白新德, 薛祥义. 稀有金属材料与工程, 2003; 32: 321)

[19] Sungjoon L, Eunae C, Sejin A, Hyuksang K. Electrochim Acta, 2001; 46: 2605

[20] Kazuo T, Masayoshi U, Mihoko O, Shinsuke Y. J Alloys Compds, 2006; 421: 303

[21] Masayoshi U. Kazuo T, Toru N, Shinsuke Y. J Alloys Compds, 2007; 446-447: 635

[22] Janos B, Gabor N, Robert S. Radiat Phys Chem, 2003; 67: 321

[23] Irving B A. Corros Sci, 1965; 5: 471

[24] Gibbs G B. Corros Sci, 1967; 7: 165

[25] Evans H E. Corros Sci, 1983; 23: 495

[26] Gellings P J, de Jongh M A. Corros Sci, 1967; 7: 413

[27] Artymowicz D M, Newman R C, Erlebacher J D. Philos Mag, 2009; 89: 1663

[28] Zhang Z M. Wang J Q, Han E H, Ke W. Corros Sci, 2011, doi: 10.1016/j.corsci.2011.07.012

[29] Fujii K, Fukuya K. Mater Trans, 2011; 52: 20

[30] Watanabe T. Res Mechanica, 1984; 11: 47

[31] Randle V. Acta Mater, 2004; 52: 4067

[32] Gertsman V Y, Bruemmer S M. Acta Mater, 2001; 49: 1589

[33] Arafin M A, Szpunar J A. Corros Sci, 2009; 51: 119

[34] Marrow T J, Babout L, Jivkov A P, Wood P, Engelberg D, Stevens N, Withers P J, Newman R C. J Nucl Mater, 2006; 352: 62

[35] King A, Johnson G, Engelberg D, Ludwig W, Marrow J. Science, 2008; 321: 382

[36] Kokawa H, Shimada M, Michiuchi M, Wang Z J, Sato Y S. Acta Mater, 2007; 55: 5401

[37] Kokawa H. J Mater Sci, 2005; 40: 927

[38] Hou J, Wang J Q, Ke W, Han E H. Mater Sci Eng, 2009; A518: 19

[39] Hou J, Peng Q J, Lu Z P, Shoji T, Wang J Q, Han E H, Ke W. Corros Sci, 2011; 53: 1137

[40] Hou J, Peng Q J, Shoji T, Wang J Q, Han E H, Ke W. Corros Sci, 2011; 53: 2956

[41] Xia S, Li H, Liu T G, Zhou B X. J Nucl Mater, 2011; doi: 10.1016/j.jnucmat.2011.06.017

[42] Hu C L, Xia S, Li H, Liu T G, Zhou B X, Chen WJ, Wang N. Corros Sci, 2011; 53: 1880

[43] Zhang Z M, Wang J Q, Han E H, Ke W. J Mater Sci Technol, 2011, accepted

[44] Meng F J, Wang J Q, Han E H, Ke W. Corros Sci, 2009; 51: 2761

[45] Meng F J, Han E H, Wang J Q, Zhang Z M, Ke W. Electrochim Acta, 2011; 56: 1781

[46] Bruemmer S M, Thomas L E. In: Shipilov S, Jones R, Olive J M, Rebak R, eds., Environment–Induced Cracking of Materials. Amsterdam: Elsevier B.V., 2008: 95

[47] Auger P, Pareige P, Welzel S, Van Duysen J C. J Nucl Mater, 2000; 280: 331

[48] Miller M K, Wirth B D, Odette G R. Mater Sci Eng, 2003; A353: 133

[49] Toyama T, Nagai Y, Tang Z, Hasegawa M, Almazouzi A, Walle E V, Gerard D R. Acta Mater, 2007; 55: 6852

[50] Miller M K, Sokolov M A, Nanstad R K, Russell K F. J Nucl Mater, 2006; 351: 187

[51] Miller M K, Russel K F. J Nucl Mater, 2007; 371: 145

[52] Miller M K, Chernobaeva A A, Shtrombakh Y I, Russell K F, Nanstad R K, Erak D Y, Zabusov O O. J Nucl Mater, 2009; 385: 615

[53] Cerezo A, Hirisawa S, Rozdilsky I, Smith G D W. Philos Trans R Soc Lond, 2003; 361A: 463

[54] Zhou B X, Wang J A, Liu Q D, Liu W Q, Wang W, Lin M D, Xu G, Chu D F. Mater China, 2011; 30: 1

(周邦新, 王均安, 刘庆东, 刘文庆, 王伟, 林民东, 徐刚, 楚大锋. 中国材料进展, 2011; 30: 1)

[55] Pareige P, Etienne A, Radiguet B. J Nucl Mater, 2009; 389: 259

[56] Etienne A, Radiguet B, Cunningham N J, Odette G R, Pareige P. J Nucl Mater, 2010; 406: 244

[57] Lozano–Perez S, Rodrigo P, Gontard L C. J Nucl Mater, 2011; 408: 289

[1]	CHEN Runnong, LI Zhaodong, CAO Yanguang, ZHANG Qifu, LI Xiaogang. Initial Corrosion Behavior and Local Corrosion Origin of 9%Cr Alloy Steel in Cl^－Containing Environment[J]. 金属学报, 2023, 59(7): 926-938.
[2]	ZHANG Qiliang, WANG Yuchao, LI Guangda, LI Xianjun, HUANG Yi, XU Yunze. Erosion-Corrosion Performance of EH36 Steel Under Sand Impacts of Different Particle Sizes[J]. 金属学报, 2023, 59(7): 893-904.
[3]	ZHAO Pingping, SONG Yingwei, DONG Kaihui, HAN En-Hou. Synergistic Effect Mechanism of Different Ions on the Electrochemical Corrosion Behavior of TC4 Titanium Alloy[J]. 金属学报, 2023, 59(7): 939-946.
[4]	SI Yongli, XUE Jintao, WANG Xingfu, LIANG Juhua, SHI Zimu, HAN Fusheng. Effect of Cr Addition on the Corrosion Behavior of Twinning-Induced Plasticity Steel[J]. 金属学报, 2023, 59(7): 905-914.
[5]	LI Xiaohan, CAO Gongwang, GUO Mingxiao, PENG Yunchao, MA Kaijun, WANG Zhenyao. Initial Corrosion Behavior of Carbon Steel Q235, Pipeline Steel L415, and Pressure Vessel Steel 16MnNi Under High Humidity and High Irradiation Coastal-Industrial Atmosphere in Zhanjiang[J]. 金属学报, 2023, 59(7): 884-892.
[6]	WANG Zongpu, WANG Weiguo, Rohrer Gregory S, CHEN Song, HONG Lihua, LIN Yan, FENG Xiaozheng, REN Shuai, ZHOU Bangxin. {111}/{111} Near Singular Boundaries in an Al-Zn-Mg-Cu Alloy Recrystallized After Rolling at Different Temperatures[J]. 金属学报, 2023, 59(7): 947-960.
[7]	WANG Bin, NIU Mengchao, WANG Wei, JIANG Tao, LUAN Junhua, YANG Ke. Microstructure and Strength-Toughness of a Cu-Contained Maraging Stainless Steel[J]. 金属学报, 2023, 59(5): 636-646.
[8]	HOU Juan, DAI Binbin, MIN Shiling, LIU Hui, JIANG Menglei, YANG Fan. Influence of Size Design on Microstructure and Properties of 304L Stainless Steel by Selective Laser Melting[J]. 金属学报, 2023, 59(5): 623-635.
[9]	XU Linjie, LIU Hui, REN Ling, YANG Ke. Effect of Cu on In-Stent Restenosis and Corrosion Resistance of Ni-Ti Alloy[J]. 金属学报, 2023, 59(4): 577-584.
[10]	WANG Jingyang, SUN Luchao, LUO Yixiu, TIAN Zhilin, REN Xiaomin, ZHANG Jie. Rare Earth Silicate Environmental Barrier Coating Material: High-Entropy Design and Resistance to CMAS Corrosion[J]. 金属学报, 2023, 59(4): 523-536.
[11]	HAN En-Hou, WANG Jianqiu. Effect of Surface State on Corrosion and Stress Corrosion for Nuclear Materials[J]. 金属学报, 2023, 59(4): 513-522.
[12]	WU Xinqiang, RONG Lijian, TAN Jibo, CHEN Shenghu, HU Xiaofeng, ZHANG Yangpeng, ZHANG Ziyu. Research Advance on Liquid Lead-Bismuth Eutectic Corrosion Resistant Si Enhanced Ferritic/Martensitic and Austenitic Stainless Steels[J]. 金属学报, 2023, 59(4): 502-512.
[13]	LIAO Jingjing, ZHANG Wei, ZHANG Junsong, WU Jun, YANG Zhongbo, PENG Qian, QIU Shaoyu. Periodic Densification-Transition Behavior of Zr-Sn-Nb-Fe-V Alloys During Uniform Corrosion in Superheated Steam[J]. 金属学报, 2023, 59(2): 289-296.
[14]	CHANG Litao. Corrosion and Stress Corrosion Crack Initiation in the Machined Surfaces of Austenitic Stainless Steels in Pressurized Water Reactor Primary Water： Research Progress and Perspective[J]. 金属学报, 2023, 59(2): 191-204.
[15]	XIA Dahai, JI Yuanyuan, MAO Yingchang, DENG Chengman, ZHU Yu, HU Wenbin. Localized Corrosion Mechanism of 2024 Aluminum Alloy in a Simulated Dynamic Seawater/Air Interface[J]. 金属学报, 2023, 59(2): 297-308.

No Suggested Reading articles found!

Viewed

Full text

Abstract

Cited

Shared

Discussed