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谭季波

  • 电话: 15840468197
  • 邮箱: jbtan10s@imr.ac.cn
  • 所属部门: 腐蚀基础与前沿研究部

研究方向

三代压水堆结构材料环境疲劳行为与评价技术研究
四代铅冷快堆结构材料环境相容性研究

代表论著

SCI论文30余篇
1.J.B. Tan, X.Q. Wu, E.-H. Han, W. Ke, X.Q. Liu, F.J. Meng, X.L. Xu. The role of TiN inclusions in fatigue behavior for Alloy 690 steam generator tube in borated and lithiated high temperature water. Corrosion Science, 88 (2014) 349-359
2.J.B. Tan, X.Q. Wu, E.-H. Han, X.Q. Liu, X.L. Xu, H.T. Sun. The effect of dissolved oxygen on fatigue behavior of Alloy 690 steam generator tubes in borated and lithiated high temperature water. Corrosion Science, 102 (2016) 394-404
3.J.B. Tan, X.Q. Liu, X.L. Xu, E.-H. Han, X.Q. Wu, X. Wang. Environmentally assisted fatigue evaluation model of Alloy 690 steam generator tube in high temperature water. Corrosion, 72(2016) 655-664
4.J.B. Tan, X.Q. Wu, E.-H. Han, W. Ke, X. Wang, H.T. Sun. Strain-rate dependent fatigue behavior of 316LN stainless steel in high-temperature water. Journal of Nuclear Materials, 489(2017) 33-41
5.J.B. Tan, Z.Y. Zhang, H. Zheng, X. Wang, J. Gao, X.Q. Wu, E.-H. Han, S.L. Yang, P.T. Huang. Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants. Journal of Nuclear Materials 541 (2020) 152407
6.J. Gao, Z.Y. Zhang, J.B. Tan (通讯作者), X.Q. Wu, E.-H. Han, W. Ke. Environmentally assisted fatigue behavior of 308L weld metal in borated and lithiated high-temperature water. Journal of Nuclear Materials. 539 (2020) 152365
7.F.Q. Ning, X. Wang, Y. Yang, J.B. Tan (通讯作者), Z.Y. Zhang, D.Jia, X.Q.Wu, E.-H. Han. Uniform corrosion behavior of FeCrAl alloys in borated and lithiated high temperature water. Journal of Materials Science & Technology. 70 (2021) ‏136-144
8.谭季波,王翔,吴欣强,韩恩厚,316LN不锈钢管状试样高温高压水的腐蚀疲劳行为,金属学报,57(2021)309-316
中国核学会团体标准6项
1,T/CNS 4—2018核电厂金属材料高温高压水中腐蚀疲劳试验方法,中国核学会团体标准, 韩恩厚,谭季波,吴欣强,张宏伟,白亚奎,王家贞,姜峨,杜东海
2,T/CNS 12—2019 压水堆核电厂金属材料环境疲劳影响模型,中国核学会团体标准,韩恩厚,谭季波,吴欣强,刘晓强,刘畅,张旭
3,T/CNS 21—2020核电厂金属材料高温高压水中微动疲劳试验方法,中国核学会团体标准,韩恩厚,谭季波,吴欣强,白亚奎,孙晨
4,T/CNS 52—2021核电厂金属材料高温高压水中环境致裂声发射原位监测试验方法,中国核学会团体标准,谭季波、张震、陈松、韩恩厚、吴欣强、徐健、陈轩、戴扬
5,HTB2021036 核电金属结构材料液态铅铋控氧环境中腐蚀浸泡试验方法,中国核学会团体标准(征求意见稿),谭季波、吴欣强、张强、韩恩厚,邓平
6,HTB2021036 核电金属结构材料液态铅铋控氧环境中慢拉伸试验方法,中国核学会团体标准(征求意见稿),谭季波、吴欣强、张强、韩恩厚,邓平
发明专利8项:
1,谭季波,吴欣强,韩恩厚,王翔,高温高压水中疲劳试样标距段应变的原位实时监测系统,发明专利,专利号:ZL 201310554160. 6,授权公告日:2016,1,13.  
2,谭季波,吴欣强,韩恩厚,张兹瑜,王翔,一种管状试样高温高压水腐蚀疲劳试验装置,发明专利,专利号:ZL 201810115400.5,授权公告日:2021,7,23.
3,谭季波,廖家鹏,钱浩,唐力晨,李晨,谢永诚,刘畅,王翔,吴欣强,一种带高温高压循环水的微动疲劳试验装置及应用,发明专利,申请号:201710282107.3,申请日,2017.4.26.
4,谭季波,吴欣强,韩恩厚,一种高温高压水微动疲劳正压力施加装置及其使用方法,发明专利,申请号:201910532846.2 申请日期:2019.6.19