张乐福

张乐福 研究员 所在系所：核科学与工程学院 办公电话：021-34204922 移动电话：13524678702 通讯地址：机动行政办公楼(A楼)318室 电子邮件：lfzhang@sjtu.edu.cn

1993－1997华中理工大学机械工程二系博士
1990－1993华中理工大学机械工程二系硕士
1986－1990华中理工大学机械工程二系学士

1997－2001，华中理工大学，材料科学与工程学院，讲师
2001－2004，日本岩手大学工学部，JSPS博士后研究员
2004－现在，上海交通大学机械与动力工程学院，副教授

2014-现在 上海新闵(东台)重型锻造公司科技副总

水冷堆核电站材料腐蚀性能评价
材料应力腐蚀/腐蚀疲劳机理研究
核电站设备老化机理与失效分析
核反应堆水化学

2007―2011 国家973项目“超临界水堆关键科学问题的基础研究”，研究骨干
2009―2011 国家自然科学基金项目“镍基690 合金晶界结构优化与耐腐蚀性研究”，负责人
2009―2010 上海核工程研究设计院项目“核电厂二回路碳钢管道流动加速腐蚀性能实验”，负责人
2010―2013 大型先进压水堆核电站重大专项重大共性技术及关键设备、材料研究课题“压水堆核电材料环境相容性研究”子课题“焊接工艺及焊后热处理方法对管道焊接件环境相容性的影响”，负责人
2010―2015 大型先进压水堆核电站重大专项重大共性技术及关键设备、材料研究课题“蒸汽发生器690合金U形管的研制和应用性能研究”，研究骨干
2014-2015 大型先进压水堆核电站重大专项“CAP1400水化学研究”
2014-2015 大型先进压水堆核电站重大专项“690合金管在高温水环境下微动磨损试验”
2015-2017 日立公司“泵、阀材料气蚀机理及可靠性研究”

2017-2021 科技部重点研发计划，应力-腐蚀-热时效耦合环境核电关键材料服役行为高通量评价技术

2019-2022 自然科学基金，晶间碳化物对镍基690合金应力腐蚀开裂的影响机理研究

2018

[1]. Lefu ZHANG, Jiamei WANG, Farzin ARJMAND, Electrochemical Behavior of Alloy 825 at High Temperature Pressurized Water Chloride Solutions (30°C to 280°C), Corrosion, 74(2018) No.11, 1245-1258.

[2]. Kai Chen, Jiamei Wang, Donghai Du*, Xianglong Guo, Lefu Zhang*. Characterizing the effects of in-situ sensitization on stress corrosion cracking of austenitic steels in supercritical water, Scripta Materialia. 158 (2019) 66-70.

[3]. Kai Chen, Jiamei Wang, et al. Investigation on the stress corrosion crack initiation and propagation behavior of Alloy 600 in high temperature water, Corrosion. online published.

[4]. Kai Chen, Jiamei Wang, Donghai Du, Xianglong Guo, Peter L. Andresen, Lefu Zhang*. Stress corrosion crack growth behavior of 310S stainless steel in supercritical water, Corrosion 74 (2018) 776-787.

[5]. Kai Chen, Jiamei Wang, Donghai Du, Peter L. Andresen, Lefu Zhang*. dK/da effects on the SCC growth rates of nickel base alloys in high-temperature water, Journal of Nuclear Materials 503 (2018) 13-21.

[6]. Xianglong Guo, Kai Chen, Wenhua Gao, Zhao Shen, Lefu Zhang*. Corrosion behavior of alumina-forming and oxide dispersion strengthened austenitic 316 stainless steel in supercritical water. Corrosion Science 138 (2018) 297-306.

[7]. Xianglong Guo, Ping Lai, Lichen Tang, Kai Chen, Lefu Zhang. Time-dependent wear behavior of alloy 690 tubes fretted against 405 stainless steel in high temperature argon and water. Wear, in press.

[8]. Xianglong Guo, Wenhua Gao, Kai Chen, Zhao Shen, Lefu Zhang*. Corrosion and stress corrosion cracking susceptibility of 347H stainless steel in supercritical water. Corrosion, 2018, 74(1): 227-236

[9]. Xianglong Guo*, Ping Lai, Lichen Tang, Junqiang Lu, Jiamei Wang, Lefu Zhang*. Fretting wear of alloy 690 tube mated with different materials in high temperature water, Wear 400-401 (2018) 119-126.

[10]. Kai Chen, Donghai Du, Wenhua Gao, Xianglong Guo, Lefu Zhang*, Peter L. Andresen. Effect of cold work on the stress corrosion cracking behavior of Alloy 690 in supercritical water environment, Journal of Nuclear Materials 498 (2018) 117-128.

[11]. Lefu Zhang, Ping Lai, Qingdong Liu, Qifeng Zeng, Junqiang Lu, Xianglong Guo*. Fretting wear behavior of zirconium alloy in B-Li water at 300℃. Journal of Nuclear Materials 499 (2018) 401-409.

[12]. Ping Lai, Xiaochuan Gao, Lichen Tang, Xianglong Guo*, Lefu Zhang. Effect of temperature on fretting wear behavior and mechanism of alloy 690 in water, Nuclear Engineering and Design 327 (2018) 51-60

[13]. Zhang L, Wang J. et al. High Temperature Electrochemical Corrosion Behavior of Fe-Cr-Ni Alloys in Simulated PWR water. CORROSION, 2018. (SCI 腐蚀研究领域顶级刊物)

[14]. 张乐福,毛新阶,刘庆冬,何龙,马武江,王元华,李志坤.蒸汽发生器下封头力学性能的均匀性分析[J].中国核电,2018,11(02):249-254.

[15]. 汪家梅,苏豪展,何琨,张乐福.电位对508Ⅲ-52M-690合金焊接接头应力腐蚀的影响[J].上海交通大学学报,2018,52(04):447-454.

[16]. 杜东海,赖平,张浩,陈凯,汪家梅,郭相龙,张乐福.316L奥氏体不锈钢在高温水中的应力腐蚀[J].腐蚀与防护,2018,39(04):274-280.

[17]. 陈凯,杜东海,陆辉,张乐福,石秀强,徐雪莲.TiN夹杂物对690合金传热管疲劳裂纹扩展行为的影响[J].稀有金属材料与工程,2018,47(04):1180-1184.

[18]. 陈凯,杜东海,陆辉,张乐福.304L不锈钢在高温高压水中的腐蚀疲劳裂纹扩展行为[J].腐蚀与防护,2018,39(01):17-23.

 

2017

[19]. Zhang L. F., Chen K., Wang J. M., Guo X. L., Du D. H., Andresen P. L. Effects of zinc injection on stress corrosion cracking of cold worked austenitic stainless steel in high-temperature water environments[J]. Scripta Materialia, 2017, 140: 50-54。(SCI)

[20]. Zhang L. F., Chen K., Du D. H., Gao W. H., Andresen P. L., Guo X. L. Characterizing the effect of creep on stress corrosion cracking of cold worked Alloy 690 in supercritical water environment[J], Journal of Nuclear Materials, 2017, 49232-40. (SCI)

[21]. Wang J. M., Zhang L. F. Effects of cold deformation on electrochemical corrosion behaviors of 304 stainless steel[J], Anti-Corrosion Methods and Materials, 2017, 64(2): 252-262. (SCI)

[22]. Wang J. M., Lu H., Zhang L. F., Meng F. J., Xu X. L. Effects of Dissolved Gas and Cold Work on the Electrochemical Behaviors of 304 Stainless Steel in Simulated PWR Primary Water[J], Corrosion, 2017 73(3): 281-289. (SCI)

[23]. Sun H. Y., Yang H. J., Wang M., Giron-Palomares B., Zhou Z. J., Zhang L. F., Zhang G. M. The corrosion and stress corrosion cracking behavior of a novel alumina-forming austenitic stainless steel in supercritical water[J],Journal of Nuclear Materials,2017, 484: 339-346. (SCI)

[24]. Guo X. L., Lai P., Tang L. C., Wang J. M., Zhang L. F.  Effects of sliding amplitude and normal load on the fretting wear behavior of alloy 690 tube exposed to high temperature water[J],Tribology International, 2017,116: 155-163. (SCI)

[25]. Gao W. H., Guo X. L., Shen Z., Zhang L. F. Corrosion behavior of oxide dispersion strengthened ferritic steels in supercritical water, Journal of Nuclear Materials,2017,486: 1-10. (SCI)

[26]. Gao W. H., Chen K., Guo X. L., Zhang L. F. Fracture toughness of type 316LN stainless steel welded joints[J]. Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing,2017, 685: 107-114. (SCI)

[27]. Chen K., Du D. H., Zhang L. F., Andresen P. L. Corrosion Fatigue Crack Growth Behavior of Alloy 690 in High-Temperature Pressurized Water[J], Corrosion, 2017, 73(6): 724-733. (SCI)

[28]. Chen K., Du D. H., Lu H., Zhang L. F. Corrosion Fatigue Crack Growth in Alloy 690[J], Rare Metal Materials and Engineering, 2017, 46(8): 2130-2136. (SCI)

[29]. Arjmand F., Zhang L. F., Wang J. M. Effect of temperature, chloride and dissolved oxygen concentration on the open circuit and transpassive potential values of 316L stainless steel at high-temperature pressurized water[J], Nuclear Engineering and Design,2017, 322: 215-226. (SCI)

[30]. Xianglong Guo, Kai Chen, Wenhua Gao, Zhao Shen, Ping Lai, Lefu Zhang. A research on the corrosion and stress corrosion cracking susceptibility of 316L stainless steel exposed to supercritical water[J], Corrosion Science, 2017, 127: 157-167. (SCI)

[31]. 陈凯,杜东海,张乐福.690合金在压水堆环境中的腐蚀疲劳裂纹扩展行为[J].上海交通大学学报,2017(11):1281-1286. （EI）

[32]. 陆辉,汪家梅,张乐福,孟凡江,石秀强.690合金的高温电化学性能[J].稀有金属材料与工程,2017,46(10):2969-2974. （SCI）

[33]. 汪家梅,Farzin Arjmand,杜东海,陈凯,赖平,高文华,张浩,郭相龙,张乐福.压水堆一回路主管道316L不锈钢的电化学腐蚀行为[J].工程科学学报,2017,39(09):1355-1363. （EI）

[34]. 孙永铎,熊茹,邱绍宇,宋怡漾,汪家梅,张乐福.国产690合金与321不锈钢异种金属焊缝的应力腐蚀行为研究[J].核动力工程,2017,38(04):153-158.

[35]. 何琨,汪家梅,张乐福.321-52M-690异种金属焊接接头的应力腐蚀开裂行为研究[J].原子能科学技术,2017,51(07):1279-1285. （EI）

[36]. 杜东海,赖平,陈凯,张乐福.焊接残余应力对316LN不锈钢应力腐蚀裂纹扩展速率的影响[J].原子能科学技术,2017,51(04):721-726. （EI）

[37]. [8]杜东海,陈凯,张乐福,石秀强,尹开锯.注锌对316不锈钢应力腐蚀裂纹扩展速率的影响[J].核动力工程,2017,38(02):78-83.

[38]. 汪家梅,陆辉,张乐福,孟凡江,徐雪莲.304不锈钢在模拟压水堆一回路水中高温电化学腐蚀行为[J].工程科学学报,2017,39(03):399-406. （EI）

[39]. 汪家梅,何琨,王理,张乐福.316NG焊接接头在含氯离子的高温高压水中应力腐蚀开裂研究[J].核动力工程,2017,38(01):72-76.

[40]. 赖平,张乐福,潘向烽,宋利君,李新民.在线测试碳钢流动加速腐蚀减薄速率的直流电压法[J].理化检验(物理分册),2017,53(01):17-21.

2016

[41]. D. Du, K. Chen, H. Lu, L. Zhang, X. Shi, X. Xu, P.L. Andresen. Effects of chloride and oxygen on stress corrosion cracking of cold worked 316/316L austenitic stainless steel in high temperature water. CORROS SCI. 110 (2016), 134-142. A

[42]. F. Arjmand, J. Wang, L. Zhang, Investigation of the corrosion inhibition of CTAB and SDS on carbon steel in presence of chloride ions using an experimental design strategy, “Journal of Materials Engineering and Performance” Doi: 10.1007/s11665-016-1903-0 (2016) 1–11. (IF = 0.998). ISSN: 1059-9495 C

[43]. 高文华,沈朝,张乐福.HR3C在超临界水中的腐蚀性能研究[J].原子能科学技术,2016,02:317-322.

[44]. 段振刚,杜东海,张乐福,孟凡江,石秀强.304和316L不锈钢的高温电化学腐蚀行为[J].上海交通大学学报,2016,02:215-221.

[45]. 刘晓强,孟凡江,徐雪莲,汪家梅,杨晨,张乐福.690合金晶间腐蚀化学浸泡试验方法的适用性[J].腐蚀与防护,2016,03:236-240.

[46]. 陈凯,杜东海,陆辉,张乐福,徐雪莲,石秀强,孟凡江,鲍一晨,刘晓强.用直流电压降法研究316LN不锈钢的疲劳裂纹扩展行为[J].机械工程材料,2016,02:7-10+36.

[47]. 沈朝,胡梦,张乐福,周张健.奥氏体ODS钢在超临界水中的腐蚀行为[J].原子能科学技术,2016,03:484-491.

[48]. 汪家梅,FarzinArjmand,张乐福.缓蚀剂SDS+CTAB复配溶液中碳钢电化学腐蚀性能的影响因素研究[J].原子能科学技术,2016,04:604-611.

[49]. 胡梦,李志军,张乐福.介质电导率对直流电压降法测试腐蚀疲劳裂纹长度准确性的影响[J].理化检验(物理分册),2016,04:221-226+230.

[50]. 胡梦,沈朝,张乐福.25Cr-20Ni-ODS钢在超临界水中的腐蚀行为[J].腐蚀与防护,2016,04:305-312.

[51]. 陆辉,沈朝,张乐福.超临界水中310-ODS钢表面氧化膜形成机制和性能[J].上海交通大学学报,2016,04:528-533.

[52]. 汪家梅,段振刚,张乐福,孟凡江,石秀强.核电蒸汽发生器690合金管在高温高压水中的腐蚀电化学行为[J].上海交通大学学报,2016,04:514-520.

[53]. 汪家梅,陆辉,段振刚,张乐福,孟凡江,徐雪莲.模拟压水堆二回路水环境中温度对690合金电化学腐蚀行为的影响[J].中国腐蚀与防护学报,2016,02:113-120.

[54]. 沈朝,汪家梅,张乐福.镍基合金C276在超临界水中的腐蚀行为[J].工程科学学报,2016,05:706-713.

[55]. 高文华,沈朝,张乐福.T91钢在超临界水环境中的腐蚀性能[J].腐蚀与防护,2016,06:444-448+502.

1.课程名称： 核反应堆材料与水化学
授课对象： 本科生
学时数： 36学时
学分：2学分
2.课程名称： 核反应堆材料
授课对象： 硕士/博士研究生
学时数： 54学时
学分：3学分

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ZL 2014 1 08206 18. 2 一种在线检测金属减薄速率的试样及方法

 

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