Please wait a minute...
材料导报  2026, Vol. 40 Issue (6): 25020036-7    https://doi.org/10.11896/cldb.25020036
  金属与金属基复合材料 |
一回路注锌对蒸汽发生器传热管钝化/氧化行为和腐蚀产物释放影响的研究与展望
魏啸天1,2, 孟凡江2, 鲍一晨2, 刘晓强2, 郑明光2, 欧阳晓平1,*
1 华北电力大学核科学与工程学院,北京 102206;
2 上海核工程研究设计院股份有限公司,上海 200233
Passivation/Oxidation Behavior and Corrosion Products Release of Heat Transfer Tubes in Steam Generators by Zinc Injection in the Primary Water of PWR:a Review
WEI Xiaotian1,2, MENG Fanjiang2, BAO Yichen2, LIU Xiaoqiang2, ZHENG Mingguang2, OUYANG Xiaoping1,*
1 School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China;
2 Shanghai Nuclear Engineering Research & Design Institute Co., Ltd., Shanghai 200233, China
下载:  全 文 ( PDF ) ( 14421KB ) 
输出:  BibTeX | EndNote (RIS)      
摘要 为进一步提高压水堆核电机组在调试、运行期间的安全可靠性,需要充分考虑关键结构部件随运行周期发生的老化,并采取必要手段进行有效控制。其中,一回路主冷却剂系统将注锌水化学(ZWC)作为缓解材料腐蚀、降低腐蚀产物释放的方案,已在国内外机组广泛使用。本文针对一回路注锌水化学与蒸汽发生器传热管钝化/氧化行为及腐蚀产物释放、输运、沉积的影响因素,主要从注锌量、注锌时机、钝化/氧化膜特性、应力腐蚀开裂(SCC)、腐蚀控制等方面开展蒸汽发生器传热管与注锌相容性的分析,并就后续注锌策略及预测技术的改进方向进行展望。
服务
把本文推荐给朋友
加入引用管理器
E-mail Alert
RSS
作者相关文章
魏啸天
孟凡江
鲍一晨
刘晓强
郑明光
欧阳晓平
关键词:  压水堆  注锌水化学  传热管  钝化/氧化  腐蚀产物    
Abstract: To further enhance the safety and reliability of pressurized water reactor(PWR) nuclear powerplants during commissioning and operational phases, it is imperative to comprehensively account for material aging in critical structural components across operational cycles while implementing necessary mitigation measures. This paper systematically investigates the compatibility between zinc-injection water chemistry(ZWC) implementation and steam generator tubes through a multi-parametric analysis, focusing on the interaction mechanisms of zinc injection with passivation/oxidation behaviors, corrosion product release-transport-deposition dynamics, and stress corrosion cracking(SCC) susceptibility. Key factors are examined through four critical dimensions:zinc injection dosage optimization, timing sequence determination, passivation/oxide film characterization, and corrosion control methodologies. Furthermore, the study proposes forward-looking improvements for zinc injection strategies, including predictive modeling integrating electrochemical kinetics, computational fluid dynamics simulations of particulate transport, and machine learning-enhanced dose-response relationships. These proposed advancements aim to establish a scientific foundation for next-generation adaptive water chemistry management systems in advanced PWR designs.
Key words:  pressurized water reactor    zinc-injection water chemistry    heat surface tube    passivation/oxidation    corrosion product
出版日期:  2026-03-25      发布日期:  2026-04-03
ZTFLH:  TG172.82  
基金资助: 国家重点研发计划(2019YFB1900902)
通讯作者:  *欧阳晓平,博士,华北电力大学核科学与工程学院教授、博士研究生导师、中国工程院院士。目前主要从事实验核物理和脉冲辐射场诊断技术方面的研究工作。oyxp2003@aliyun.com   
作者简介:  魏啸天,华北电力大学大学核科学与工程学院博士研究生,在欧阳晓平教授的指导下开展大型先进压水堆核电站注锌水化学策略及控制的研究。
引用本文:    
魏啸天, 孟凡江, 鲍一晨, 刘晓强, 郑明光, 欧阳晓平. 一回路注锌对蒸汽发生器传热管钝化/氧化行为和腐蚀产物释放影响的研究与展望[J]. 材料导报, 2026, 40(6): 25020036-7.
WEI Xiaotian, MENG Fanjiang, BAO Yichen, LIU Xiaoqiang, ZHENG Mingguang, OUYANG Xiaoping. Passivation/Oxidation Behavior and Corrosion Products Release of Heat Transfer Tubes in Steam Generators by Zinc Injection in the Primary Water of PWR:a Review. Materials Reports, 2026, 40(6): 25020036-7.
链接本文:  
https://www.mater-rep.com/CN/10.11896/cldb.25020036  或          https://www.mater-rep.com/CN/Y2026/V40/I6/25020036
1 Sun H H. Third generation nuclear power technology — AP1000, China Electric Power Press, China, 2016,pp. 1(in Chinese).
孙汉虹. 第三代核电技术——AP1000, 中国电力出版社, 2016, pp. 1.
2 Zheng M G, Yan J Q. Large advanced passive pressurized water reactor CAP1400, Shanghai Jiaotong University Press, China, 2018, pp. 157(in Chinese).
郑明光, 严锦泉. 大型先进非能动压水堆CAP1400. 上海交通大学出版社, 2018, pp. 157.
3 Bojinov M, Kinnunen P, Lundgren K, et al. Journal of the Electroche-mical Society, 2005, 152, B250.
4 Hur D H, Lim D S, Jeon S H, et al. Journal of Nuclear Materials, 2021, 555, 153147.
5 Chajduk E, Bojanowska-Czajka A. Progress in Nuclear Engergy, 2016, 88, 1.
6 Ocken H, Fruzzetti K, Frattini P, et al. Power Plant Chemistry, 2002, 4, 261.
7 Bergmann C A, Gold R E, Sejvar J, et al. In:Water Chemistry of Nuclear Reactor Systems 7. Bournemouth, UK, 1996, pp. 287.
8 Betova I, Bojinov M, Kinnunen P, et al. 2011 VTT Report.
9 EPRI. Development of a zinc pretreatment method for corrosion product management:radiation field and fuel CRUD source terms, EPRI, USA, 2021, pp. 3002018225.
10 Liao J P, Hu Y S, Li J G, et al. Nuclear Engineering and Technology, 2021, 54, 984.
11 Mino Y, Nakahama S, Aizawa Y, et al. In:Nuclear Plant Chemistry Conference, Paris, France, 2012, pp. 33.
12 Borisevich V D, Pavlov A V, Okhotina I A, et al. Applied Radiation & Isotopes, 2009, 67, 1167.
13 Arjmand Y G. Materials Characterization, 2021, 177, 1.
14 Liu X H, Wu X Q, Han E H, et al. Corrosion Science, 2012, 65, 136.
15 Hai Z Y, Wang H, Xin C S, et al. Journal of Chinese Society for Corrosion and Protection, 2014, 34(3), 532(in Chinese).
海正银, 王辉, 辛长胜, 等. 中国腐蚀与防护学报, 2014, 34(3), 532.
16 Jeon S H, Lim D S, Jin S C, et al. Materials, 2021, 14, 4105.
17 Arjmand F, Wang J M, Zhang L, et al. Journal of Alloys and Compounds, 2019, 791, 1176.
18 Duan Z G, Pan X F, Zhang L F, et al. Corrosion & Protection, 2014, 35(4), 218(in Chinese).
段振刚, 潘向烽, 张乐福, 等. 腐蚀与防护, 2014, 35(4), 218.
19 Duan Z G, Zhang L F, Jiang S Q, et al. Corrosion & Protection, 2014, 35(3), 224. (in Chinese)
段振刚, 张乐福, 姜苏青, 等. 腐蚀与防护, 2014, 35(3), 224.
20 Jiang Y F, Bustillo K C, Devine T M. Corrosion and Materials Degradation, 2023, 4, 54.
21 EPRI. Pressurized water reactor primary zinc application sourcebook, Revision 1, EPRI, USA, 2012, pp. 1025316.
22 Huang J B, Liu X H, Han E H, et al. Corrosion Science, 2011, 53, 3254.
23 Duan Z G, Du D H, Wang L, et al. Corrosion Science and Protection Technology, 2014, 26(3), 218(in Chinese).
段振刚, 杜东海, 王力, 等. 腐蚀科学与防护技术, 2014, 26(3), 218.
24 Morton D S, Thompson C D, Gladding D, et al. KAPL Atomic Power Laboratory Reports, USA, 1997, pp. 1.
25 Wu X Q, Liu X H, Zhang Z Y, et al. Corrosion Communications, 2022, 6, 52.
26 Hayakawa H, Mino Y, Nakahama S, et al. In:Nuclear Plant Chemistry Conference. Paris, France, 2012.
27 Lim D S, Jeon S H, Bae B J, et al. Corrosion Science, 2021, 189, 109627.
28 Bojinov M, Betova I, Karastoyanov V. Metals, 2025, 15, 1242.
29 Devito R L, Buckley D J, Byers W A, et al. Westinghouse Experience with AP1000 plant hot functional testing chemistry, Westinghouse Electric Company Reports, USA, 2016.
30 Lin C C, Smith F R, Cowan R L. Nuclear Engineering and Design, 1996, 166, 31.
31 Beverskog B, Puigdomenech I. Corrosion Science, 1997, 39, 107.
32 Zhang S H, Tan Y, Liang K X. Materials Letter, 2012, 68, 36.
33 Rak Z, Brenner D W. Applied Surface Science, 2017, 402, 108.
34 Sun L, Chen S, Zhao T Y, et al. Corrosion Science, 2022, 209, 110759.
35 Zhao T Y, Chen S, Qiu J, et al. Corrosion Science, 2024, 237, 112293.
36 Yin X R, Sun X F, Wang H T, et al. Solid State Communications, 2020, 321, 114040.
37 Bonnet M L, Costa D, Protopopoff E, et al. Applied Surface Science, 2017, 426, 788.
38 EPRI. Materials reliability program:mitigation of stress corrosion crack growth in nickel-based alloys in primary water by hydrogen optimization and zinc addition(MRP-280). Polo Alto, CA, USA, 2010, pp. 1021013.
39 Angell M G, Allan S J, Airey G P. In:Ninth International Symposium on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors. Newport Beach, CA, USA, 1999.
40 Kawamura H, Hirano H, Shirai S, et al. Corrosion, 2000, 56, 623.
41 EPRI. Materials reliability program, effect of zinc addition on mitigation of primary water stress corrosion cracking of alloy 600(MRP-78), EPRI, USA, 2002, pp. 1003522.
42 Moss T, Kuang W J, Was G S. Current Opinion in Solid State and Materials Science, 2018, 22, 16.
43 Ziemniak S E, Hanson M. Corrosion Science, 2006, 48, 3330.
44 EPRI. Corrosion behavior of steam generator tubing exposed to reactor coolant, EPRI, USA, 2006, pp. 1003601.
45 Tian C, Xia M M, Huang B C, et al. Atomic Energy Science and Technology, 2021, 55(11), 2107(in Chinese).
田超, 夏明明, 黄博琛等. 原子能科学技术, 2021, 55(11), 2107.
46 Thornton E W. In:Coolant technology of water cooled reactors. IAEA Reports, 1992, pp. 9.
47 Orlenkov I S, Moskvin L N, Gusev B A, et al. Radiochemistry, 2010, 52, 596.
48 IAEA. Modelling of transport of radioactive substances in the primary circuit of water-cooled reactors, IAEA, Vienna, Austria, 2012, pp. 1.
49 Allsop H. Briden B L. Burrill K A. In:Proceedings of the International Symposium on Activity Transport in Water Cooled Nuclear Power Reactors, AECL report RC-1334, 1994.
50 Lee C B. Modeling of corrosion product transport in PWR primary system. Ph.D.Thesis, Massachusetts Institute of Technology, USA, 1990.
51 Zmitko M. In:Proceedings of Second Research Coordination Meeting for the IAEA CRP on Activity Transport Modelling. Vienna, Austria, 1998.
52 Dinov K. Nuclear Technology, 1991, 94, 281.
53 Tarabelli D, Antoni S. IAEA benchmark on modeling on radioactive substances in primary circuit of water cooled reactors, CEA report NT-SECA-LTC-165, 1998.
54 Kim K S, Shim H S, Baek S H, et al. In:Korean Nuclear Society Autumn Meeting. 2019, Goyang, Korea, pp. 1.
55 Hur D H, Kim K S, Shim H S, et al. Materials, 2020, 13, 4317.
56 Kim K S, Baek S H, Shim H S, et al. Annals of Nuclear Energy, 2020, 146, 107643.
57 Xue C C, Zhang Z Y, Tan J B, et al. Corrosion Science, 2022, 211, 110909.
58 Xue C C, Liu X H, Chen Z C, et al. Journal of Nuclear Materials, 2024, 599, 155210.
[1] 方园, 李钰, 景嘉哲, 范仕敏, 韩润润, 武文玲, 罗宏杰, 朱建锋. 腐蚀产物加速青铜腐蚀的电催化氧还原机理研究[J]. 材料导报, 2025, 39(24): 24120139-6.
[2] 郭贺, 焦进超, 张津, 王旭东, 连勇, 冯波, 冯晓伟, 郑开宏, 丁啸云, 韩东. 不同铝合金对Al/Mg/Al层状复合材料腐蚀行为的影响[J]. 材料导报, 2024, 38(12): 22090163-8.
[3] 赵冠琳, 刘树帅, 吴东亭, 王新洪, 邹勇. 元素W与Mo对非晶Ni-P镀层热稳定性和耐腐蚀性能的影响[J]. 材料导报, 2023, 37(7): 21070071-7.
[4] 杨贵荣, 宋文明, 潘照霞, 马颖, 郝远. 气相压力对CO2/H2O气液两相泡状流中20#钢初期腐蚀行为的影响[J]. 材料导报, 2022, 36(24): 21110057-6.
[5] 林震霞, 党莹, 徐祺, 李丹. 690合金在核电厂一、二回路工况下的均匀腐蚀性能研究[J]. 材料导报, 2020, 34(Z2): 437-440.
[6] 杨贵荣,宋文明,董雪娇,张玉福,王富强,李 健,马 颖. CO2分压对20#钢在CO2/H2O气液两相塞状流中腐蚀行为的影响[J]. 《材料导报》期刊社, 2018, 32(9): 1557-1563.
[7] 秦建伟, 罗丽珠, 帅茂兵. 金属铀的水蒸气腐蚀行为研究现状*[J]. 《材料导报》期刊社, 2017, 31(13): 17-24.
[1] Yimeng XIA, Shuai WU, Feng TAN, Wei LI, Qingmao WEI, Chungang MIN, Xikun YANG. Effect of Anionic Groups of Cobalt Salt on the Electrocatalytic Activity of Co-N-C Catalysts[J]. Materials Reports, 2018, 32(3): 362 -367 .
[2] ZHOU Rui, LI Lulu, XIE Dong, ZHANG Jianguo, WU Mengli. A Determining Method of Constitutive Parameters for Metal Powder Compaction Based on Modified Drucker-Prager Cap Model[J]. Materials Reports, 2018, 32(6): 1020 -1025 .
[3] GUO Linkai, WANG Lei, ZHANG Qing. Some Research Developments on Mechanical Property of Nanoporous Metals[J]. Materials Reports, 2017, 31(1): 97 -102 .
[4] ZHANG Xuerong, HU Yinchun, XI Shaohui, WANG Zhaowei, ZHAN Yan, HUANG Di, HU Chaofan, WEI Yan. Synthesis and Characterization of β-Cyclodextrin/Ag-graphene-based Electrospun Fiber Membranes for Antibiosis[J]. Materials Reports, 2018, 32(4): 545 -548 .
[5] WANG Wenjin, WANG Keqiang, YE Shenjie, MIAO Weijun, CHEN Zhongren. Effect of Asymmetric Block Copolymer of PI-b-PB on Phase Morphology and Properties of IR/BR Blends[J]. Materials Reports, 2017, 31(2): 96 -100 .
[6] MA Hao, YANG Ruixia, LI Chunjing. Advances in 2D Transition Metal Dichalcogenides[J]. Materials Reports, 2017, 31(3): 7 -14 .
[7] WANG Lan, HOU Chenxi, FAN Long, XIE Yi, LU Xirui. Research Progress in Immobilization of Sr and Cs by Mineral Materials[J]. Materials Reports, 2017, 31(3): 106 -111 .
[8] . Effect of Fe and Ce Content on Mechanical Properties and Corrosion
Resistance of Galfan Alloy
[J]. Materials Reports, 2017, 31(4): 56 -59 .
[9] . Study on Effect of Block Copolymer PS-b-PMMA on Compatibility of PCHMA/
PMMA Blends: Influences of Block Ratio, Molecular Weight and Viscosity
[J]. Materials Reports, 2017, 31(4): 87 -93 .
[10] SHI Tingting, JI Dongfang, YU Yanmin. Advances in Porphyrin Aggregation Behavior[J]. Materials Reports, 2017, 31(5): 46 -52 .
Viewed
Full text


Abstract

Cited

  Shared   
  Discussed