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个人简介

教育背景 2012.09-2017.06 中国科学技术大学 核能科学与工程 博士(导师:吴宜灿 教授) 2008.09-2012.06 山东大学 应用物理学 学士 工作经历 2021.07-至 今 上海交通大学 机械与动力工程学院 副教授 2018.07-2021.06 中山大学 中法核工程与技术学院 博士后 2017.06-2018.06 中国科学院 合肥物质科学研究院 助理研究员 科研项目 2020.01-2022.12 国家自然科学基金 青年科学基金项目 ,主持 2021.01-2023.12 广东省自然科学基金 面上项目,主持 2019.05-2021.05 中国博士后科学基金 特别资助项目(站中),主持 2018.12-2021.05 中国博士后科学基金 面上项目(一等),主持 2021.10-2023.09 清华大学 先进反应堆工程与安全教育部重点实验室 开放基金,主持 2018.07-2023.03 国家重点研发计划 国家磁约束聚变能发展研究专项,参与 代表性论文专著 研究成果先后发表在国内权威期刊中国科学和国际TOP期刊Renew. Sust. Energ. Rev. (IF=16.799),J. Hazard. Mater. (IF=14.224),Environ. Pollut. (IF=9.988),J. Hydrol. (IF=6.708),Chemosphere (IF=8.943)等刊物,部分入选期刊封面文章。 学术会议邀请、主题、口头报告: 【1】第四届全国氚科学与技术学术交流会, 海南海口, 2023. [分会场邀请报告,分会场主席] 【2】中国科学院青年创新促进会化学与材料分会2023年学术年会暨第一届“化学材料青年前沿论坛”, 上海, 2023. [特邀报告,分会场主席] 【3】中国辐射防护学会2022年学术年会 第二届青年论坛, 线上, 2022. 【4】中国核工业教育学会2022年首届学术年会, 海南海口, 2022. [优秀学术论文奖] 【5】第二届中国磁约束聚变能大会,安徽合肥,2021. 【6】The 8th International Workshop on Fluid Flow Heat Transfer and Turbulent Drag Reduction, Qingdao, China. 2021. [Keynote, Co-Chair] 【7】第十届反应堆物理与核材料学术研讨会, 上海, 2021. [优秀报告奖] 【8】中国辐射防护学会2020年学术年会, 广东惠州, 2020. [优秀报告奖] 【9】中国辐射防护学会放射生态分会2020年会暨第六届“辐射与环境”专题研讨会, 四川绵阳, 2020. 【10】中国辐射防护学会2019年学术年会, 福建福州, 2019. 【11】第三届中国氚科学与技术学术交流会, 江苏苏州, 2019. [优秀报告奖] 【12】中国辐射防护学会2018年学术年会, 广东广州, 2018. [主题报告] 【13】2nd Asia-Pacific Symposium on Tritium Science, California, USA. 2017. [Invited talk] 【14】27th IEEE Symposium On Fusion Engineering, Shanghai, China. 2017. 【15】第二届中国氚科学与技术学术交流会, 四川成都, 2017. 【16】1st IAEA Technical Meeting on Safety, Design, and Technology of Fusion Power Plants, Vienna, Austria. 2016. 【17】1st Asia-Pacific Symposium on Tritium Science, Mianyang, China. 2015. [Young Researcher Award] 【18】首届中国氚科学与技术学术交流会, 四川成都, 2015. 【19】7th US-PRC Magnetic Fusion Collaboration Workshop, Nanjing, China. 2014. 【20】第15届反应堆数值计算与粒子输运学术会议暨2014年反应堆物理会议, 四川成都, 2014. 授权专利: 【1】聂保杰, 吴宜灿, 王明煌, 倪木一. 一种基于植物氚监测数据的事故氚源项反演方法. 授权号: CN106844996B, 授权日期: 2020.04.

研究领域

1)核素多介质环境迁移转化行为 2)核应急与事故后果评价 3)聚变堆燃料循环与氚自持 4)聚变堆氚、粉尘安全分析

近期论文

查看导师新发文章 (温馨提示:请注意重名现象,建议点开原文通过作者单位确认)

【1】聂保杰, 陈德仪, 王亮, 郑善良, 谢锋, 李厚文, 朱月龙, 李凤臣, 王德忠*. 多形态氚的环境行为及辐射评价系统研究进展. 中国科学: 技术科学, 2023, http://engine.scichina.com/doi/10.1360/SST-2022-0356. 【2】Deyi Chen, Baojie Nie*, Bing Dong, Derui Yang, Siyuan Wu, Jinpeng He, Weiguo Gu, Dezhong Wang*. Insights into near-surface distribution characteristics of multi-form tritium with consideration of atmospheric buoyancy and gravitational deposition. Chemosphere, 2023, 312: 137231. 【3】Baojie Nie, Siyuan Wu, Derui Yang, Deyi Chen, Weiguo Gu, Wentao Zhou, Junlian Yin, Dezhong Wang*. Quantitative prediction of dynamic HTO migration behavior in the soil and non-negligible evapotranspiration effect. Journal of Hazardous Materials, 2022, 425: 127772. 【4】Baojie Nie, Sheng Fang, Man Jiang, Laishun Wang, Muyi Ni, Jiye Zheng, Zhiyi Yang*, Fengchen Li*. Anthropogenic tritium: inventory, discharge, environmental behavior and health effects. Renewable & Sustainable Energy Reviews, 2021, 135: 110188. 【5】Baojie Nie, Muyi Ni*, Shiping Wei. Individual dose due to radioactivity accidental release from fusion reactor. Journal of Hazardous Materials, 2017, 327: 135–143. 【6】Baojie Nie, Jinmin Yang, Wei Wang, Zhixing Gu, Yuan Yuan, Fengchen Li*. Numerical study on tritium dispersion in coastal waters: The case of Hangzhou Bay, China. Journal of Hydrology, 2020, 590: 125532. 【7】Baojie Nie, Muyi Ni*, Jinchao Liu, Zhilin Zhu, Zuolong Zhu, Fengchen Li*. Insights into potential consequences of fusion hypothetical accident, lessons learnt from the former fission accidents. Environmental Pollution, 2019, 245: 921–931. 【8】Baojie Nie, Guangming Ran, Qin Zeng, Hongfei Du, Zaixin Li, Yanjing Chen, Zuolong Zhu, Xueli Zhao, Muyi Ni*, Fengchen Li*. Insights into fuel start-up and self-sufficiency for fusion energy: The case of CFETR. Energy Science & Engineering, 2019, 7: 457–468. 【9】Baojie Nie, Jinmin Yang, Yuan Yuan, Fengchen Li*. Additional radiation dose due to atmospheric dispersion of tritium evaporated from a hypothetical reservoir. Applied Radiation and Isotopes, 2021, 167: 109475. 【10】Baojie Nie, Man Jiang, Muyi Ni*, Fengchen Li*. Preliminary environmental radiation considerations for CFETR. Fusion Engineering and Design, 2019, 140: 16–22. 【11】Baojie Nie, Muyi Ni*, Jieqiong Jiang, Yican Wu. Dynamic evaluation of environmental impact due to tritium accidental release from the fusion reactor. Journal of Environmental Radioactivity, 2015, 148: 137–140. 【12】Baojie Nie, Muyi Ni*, Chao Lian, Jieqiong Jiang. Preliminary analysis of public dose from CFETR gaseous tritium release. Fusion Engineering and Design, 2015, 91: 25–29. 【13】Baojie Nie, Muyi Ni*, Jieqiong Jiang, Yican Wu. A dynamic modeling 3H transfer to the environment under accidental release from the fusion reactor. Journal of Fusion Energy, 2015, 34: 739–745. 【14】聂保杰, 倪木一, 廉超, 宋勇, 吴宜灿. 基于湍流扩散理论的氚大气弥散程序开发与校验. 原子能科学与技术, 2013, 47: 541–546. 【15】Man Jiang, Baojie Nie, Zhangcan Yang, Muyi Ni, Zhiquan Chen. First principles investigation of hydrogen adsorption and dissociation on Fe doped α-Al2O3 (0001) surface. Journal of Nuclear Materials, 2020, 533: 152102. 【16】Zuolong Zhu, Baojie Nie, Dehong Chen. A system dynamics model for tritium cycle of pulsed fusion reactor. Fusion Engineering and Design, 2017, 118: 5–10. 【17】Xueli Zhao, Muyi Ni, Baojie Nie, Bing Zhang, Lei Chen, Kai Huang, Songlin Liu*. 3D tritium transport analysis for WCCB blanket based on COMSOL. Fusion Engineering and Design, 2020, 151: 111405. 【18】Muyi Ni, Chao Lian, Shichao Zhang, Baojie Nie, Jieqiong Jiang*. Structural design and preliminary analysis of liquid lead-lithium blanket for china fusion engineering test reactor. Fusion Engineering and Design, 2015, 94: 61–66. 【19】Wei Wang, Wei Liu, Qin Zhang, Xun Ding, Baojie Nie, Dongxun Zhang, Xinxin Chu. Distribution of 137Cs in different soil particle sizes in the vicinity of the Qinshan nuclear power plant. Journal of Radioanalytical and Nuclear Chemistry, 2020, 326: 1663–1668. 【20】Laishun Wang, Kai Wang, Nejdet Erkan, Yuan Yuan, Jiayue Chen, Baojie Nie, Fengchen Li*, Koji Okamoto. Metal materials surface wettability increase induced by electron beam irradiation. Applied Surface Science, 2020, 511: 145555. 【21】Zhixing Gu, Qingxian Zhang, Yi Gu, Liangquan Ge, Guoqiang Zeng, Muhao Zhang, Baojie Nie. Verification of a self-developed CFD-based multi-physics coupled code MPC-LBE for LBE-cooled reactor. Nuclear Science and Techniques, 2021, 32: 52. 【22】吴宜灿, 郁杰, 胡丽琴, 等. 聚变堆安全特性评价研究. 核科学与工程, 2016, 36: 802–810.

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