吴彬 - 清华大学 - 核能与新能源技术研究院

个人简介

教育背景学士 200407 清华大学机械工程及自动化博士 200907 清华大学材料科学与工程工作履历 200908 - 201312 清华大学核研院助理研究员 201312 – 至今清华大学核研院副研究员 201808 – 至今清华大学核研院院党委副书记学术兼职 2014 – 至今机械工程学会高级会员 2010 – 至今注册核安全工程师研究概况 2012 –至今华能石岛湾高温气冷堆核电站示范工程国家科技重大专项项目 2017 –2020 多模块高温气冷堆设计标准化研究国家科技重大专项课题 2018 –2020 中印尼高温气冷堆联合实验室政府间国际科技创新合作重点专项 2018 –2019 燃料装卸系统调试方法及关键技术研究国家科技重大专项课题 2018 –2019 碰撞摩擦耦合作用下燃料元件壳体石墨材料去除行为研究清华大学自主科研计划课题 2012 –2017 高温气冷堆乏燃料贮存关键技术研究及工程验证国家科技重大专项课题 2014 –2016 自润滑钨基复合材料的制备与摩擦学性能国家自然科学基金青年基金奖励与荣誉 2015 三等奖中船重工集团科学技术奖

研究领域

依托高温气冷堆重大专项团队，研究核燃料装卸与贮存，气力输送的流体问题，核石墨材料，耐辐照耐磨材料等。着力研究工程中的科学技术问题

近期论文

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Wu B, Wang J, Zhong L, et al. Sliding Wear of WC-Ni-Based Self-Lubricating Composites With the Addition of Fullerene-Like WS2 Nanoparticles Against WC-Ni Cermet. ASME Journal of Tribology, 2020, 142(4): 044501. Wang J, Li Y, Wu B, Hao Y, Wang H. Commissioning Technology Research of Spent Fuel Storage Residual Heat Removal System of HTR-PM .The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2019, Tsukuba, Ibaraki, Japan. Wu B, Li Y, Zhao H, et al. Wear behavior of graphitic matrix of fuel elements used in pebble-bed high-temperature gas-cooled reactors against steel. Nuclear Engineering and Design 2018, 328:353-358. Zheng Z, Zhao H, Li Z, Liu X, Wu B, Liu B. Research on microstructure and oxidation resistant property of ZrSi2 -SiC/SiC coating on HTR graphite spheres. Ceramics International 2018, 44(5):4795-4800. Wang B., Wu B., Uddin R., Jia H., Wang J. Development of a thermal-hydraulic analysis code TAC-DS for spent fuel dry-storage system for high-temperature pebble bed reactor Journal of Nuclear Science and Technology 2017, 1:1-18. Huang X, Wang J, Zhang H, Ren J, Zan Q, Gong Q, Wu B*. WC-Ni-Cr-based self-lubricating composites fabricated by pulsed electric current sintering with addition of WS2 solid lubricant. International Journal of Refractory Metals and Hard Materials, 2017, 66: 158-162. Wang J, Wang B, Wu B, Li Y. Design of the spent fuel storage well of HTR-PM. 24th International Conference on Nuclear Engineering, 2016, Charlotte, North Carolina, USA. Wang J, Li Y, Wu B. Research and experiment on the key technologies of the spent fuel storage in HTR-PM. 24th International Conference on Nuclear Engineering, 2016, Las Vegas, NV, United states. Zhu Y, Zhou A, Ji Y, Jia J, Wang L, Wu B, Zan Q. Tribological properties of Ti3SiC2 coupled with different counterfaces. Ceramics International, 2015, 41(5): 6950-6955. Wang J, Liu X, Wang B, Li Y, Wu B. Design of the ground crane and shielding cask for the spent fuel canister of HTR-PM. 23rd International Conference on Nuclear Engineering, 2015, Chiba, Japan. Wu B, Gong Q, Song H, et al. Prickly structure of multi-walled carbon nanotube reinforced mesocarbon microbead composite with high strength at elevated temperature. Composites Part B: Engineering, 2014, 56: 876-881. Wu B, Wang J, Li Y, et al. Retrieving fuel elements by pneumatic suction in pebble-bed high temperature gas-cooled reactor. 22nd International Conference on Nuclear Engineering, ICONE, 2014, Prague, Czech Republic. Wu B, Wang J, Li Y, Liu J. Electromagnetic self-locking device for air cylinders in spent fuel storage system of pebble-bed high temperature gas-cooled reactor.21st International Conference on Nuclear Engineering, 2013, Chengdu, China.