卢凯（Lu Kai）

研究员/博导，hbs02红宝石线路核能技术研究所所长

最高学历：

日本福井大学，工学博士

研究领域：

基于确定断裂力学（DFM）的结构完整性评估方法，包括辐照材料断裂韧性的尺寸效应及分散性、裂尖拘束效果、裂纹扩展分析，韧脆转变区材料的失效机理、反应堆流-热-固多场耦合分析、数据驱动断裂力学计算、承压设备安全评估规范等。

基于概率断裂力学（PFM）的核电设备安全评估方法，包括不确定性与可靠性理论、断裂韧性分布模型、贝叶斯更新、结构失效概率分析等。

Email： lu.kai@fzu.edu.cn

教育工作经历：

2023-至今：hbs02红宝石线路，化工学院，研究员/博导

2018-2023：日本原子能研究机构，核安全研究中心，研究员（tenure track）

2015-2018：日本原子能研究机构，核安全研究中心，博士后，合作导师：李银生研究员（日本工程院院士）

2012-2015：日本福井大学，核能与能源安全专业，博士，导师：Toshiyuki Meshii教授（日本原子能学会会士）

2010-2012：日本福井大学，核能与能源安全专业，硕士，导师：Toshiyuki Meshii教授

2005-2009：北京信息科技大学，车辆工程，学士

（2008-2009：日本福井大学，核能与能源安全，交换留学）

个人简介：

卢凯博士，hbs02红宝石线路研究员，福建省“闽江学者”特聘教授。主要从事承压设备的结构完整性评估方法及应用研究，在断裂力学、压力容器等领域的专业期刊（Engineering Fracture Mechanics、Theoretical and Applied Fracture Mechanics、International Journal of Pressure Vessels and Piping、Journal of Pressure Vessel Technology）发表论文30余篇，出版技术类专著2部，参加ASME PVP、ICONE、ECF等领域内国际会议并做报告20多次，参与修订国际行业标准多项，负责开发了日本唯一的核反应堆压力容器失效概率分析软件PASCAL5。

科研项目：

主持（参与）国内外核电领域的基础研究及重大专项10余项，回国前长期担任日本原子能研究委员会、日本机械学会核电设备标准委员会的委员。

1.国家自然科学基金（面上项目），在役反应堆压力容器失效风险量化与安全裕度调控研究，52475151, 2025.01-2028.12，负责人。

2.欧洲原子能共同体（Horizon 2020 Programme国际合作项目），Advanced PTS Analysis for LTO，No. 945253, 2020.01-2024.12，参与人。

3.日本原子能研究机构（共同研究项目），概率断裂力学分析软件PASCAL4的可靠性验证研究，2020.04-2022.03，负责人。

4.日本原子能规制厅（核能重大专项），老化设备技术评估（核反应堆一回路设备结构完整性评价方法改进），2016-2019，参与人。

代表性论文：

1.T. Zhang, X. Shang, N. Zhang,K. Lu^*, M. Xie, An investigation on fracture toughness predictions from mini-sized uniaxial tensile specimens with global and local approaches, Theoretical and Applied Fracture Mechanics, 131 (2024), 104366

2. K. Lu, H. Takamizawa, Y. Li* et al., Verification of probabilistic fracture mechanics analysis code PASCAL for reactor pressure vessel, JSME Mechanical Engineering Journal, 10(4), 2023.

3. K. Lu, J. Katsuyama, H. Takamizawa, Y. Li*, Guideline on structural integrity assessment for reactor pressure vessel in domestic light water reactor based on probabilistic fracture mechanics (in Japanese), JAEA-Research 2022-012, DOI:10.11484/jaea-research-2022-012.

4. K. Lu, H. Takamizawa, J. Katsuyama, Y. Li*, Recent improvements of probabilistic fracture mechanics analysis code PASCAL for reactor pressure vessels, International Journal of Pressure Vessels and Piping, 199 (2022), 104706.

5. K. Lu, J. Katsuyama, K. Masaki., T. Watanabe, Y. Li*, Effect of coolant water temperature of emergency core cooling system on failure probability of reactor pressure vessel, Journal of Pressure Vessel Technology, 143 (2021) 031704.

6. T. Meshii, K. Lu^*,Y. Fujiwara, Extended investigation of the test specimen thickness (TST) effect on the fracture toughness (Jc) of a material in the ductile-to-brittle transition temperature region as a difference in the crack tip constraint- What is the loss of constraint in the TST effects on Jc? Engineering Fracture Mechanics, 135 (2015), 286-294.

7. K. Lu^*, T. Meshii, A systematic investigation of T-stresses for a variety of center-cracked tension specimens, Theoretical and Applied Fracture Mechanics, 77 (2015), 74-81.

获得奖项及荣誉：

2023年 日本原子能研究机构 研发功绩奖

2023年 泉州市“桐江学者”特聘教授

2022年 福建省“闽江学者”特聘教授

2019年 日本机械学会JSME论文表彰（国际核工程大会ICONE27）

2017年 日本原子能研究机构 研发功绩奖

2015年 日本福井大学 成果显著奖

2012年 美国机械工程师协会ASME优秀论文奖（压力容器与管道会议PVP2012）

核电站是高技术集成项目，维护核电安全需要物理、化学、机械、材料、力学、控制、计算机等几乎所有学科的知识储备。希望志同道合的青年教师一起加入我们的核电装备结构完整性研究团队，为中国核电技术从大到强贡献力量。也欢迎对核电与新能源装备安全、金属材料失效分析、力学实验+有限元模拟、概率统计分析、软件编程等领域感兴趣的同学参与学习研究。

English CV

Highest Academic：

University of Fukui (Japan)，Doctor of Engineering

Research Field：

l Structural integrity assessment method based on deterministic fracture mechanics, including size effect/scatter of fracture toughness、crack-tip constraint, crack propagation analysis, failure mechanism of materials in DBTT, coupled fluid/solid thermal analysis for RPV、data-driven fracture mechanics、fitness-for-service codes of pressure equipment.

l Structural integrity assessment method based on probabilistic fracture mechanics, including theories of uncertainty and reliability, fracture toughness distribution, Bayesian inference, failure probability analysis of components.

Email： lu.kai@fzu.edu.cn

Education-Working Experience：

2023 to present：Fuzhou University, college of chemical engineering, professor

2018-2023：JAEA，nuclear safety research canter, researcher (tenure track)

2015-2018：JAEA，nuclear safety research canter, post-doctoral fellow

2012-2015：University of Fukui, nuclear power & safety engineering, Ph. D

2010-2012：University of Fukui, nuclear power & safety engineering, M.S.

2005-2009：Beijing Information Science & Technology Univ., Vehicle engineering, B.S.

（2008-2009：University of Fukui, nuclear power & safety engineering, exchange）

Self-Introduction：

Dr. Lu Kai working in Fuzhou Univ. was selected for the “Minjiang Scholars” Program of Fujian Province. His main research interests relate to development and application of structural integrity assessment method for pressure equipment. In the past, he has published over 30 journal papers and 2 technical documents, presented more than 20 times in international conferences, made contributions to revisions of several industry standards. In addition, his team in JAEA developed the sole PFM analysis code for RPVs in Japan (besides FAVOR in the U.S., PASCAL is the second practical tool for NPP license renewal discussion in the world).

Selected Paper：

1. K. Lu, H. Takamizawa, Y. Li^* et al., Verification of probabilistic fracture mechanics analysis code PASCAL for reactor pressure vessel, JSME Mechanical Engineering Journal, 10(4), 2023.

2. K. Lu, J. Katsuyama, H. Takamizawa, Y. Li^*, Guideline on structural integrity assessment for reactor pressure vessel in domestic light water reactor based on probabilistic fracture mechanics (in Japanese), JAEA-Research 2022-012, DOI:10.11484/jaea-research-2022-012.

3. K. Lu, H. Takamizawa, J. Katsuyama, Y. Li^*, Recent improvements of probabilistic fracture mechanics analysis code PASCAL for reactor pressure vessels, International Journal of Pressure Vessels and Piping, 199 (2022), 104706.

4. K. Lu, J. Katsuyama, K. Masaki., T. Watanabe, Y. Li^*, Effect of coolant water temperature of emergency core cooling system on failure probability of reactor pressure vessel, Journal of Pressure Vessel Technology, 143 (2021) 031704.

5. T. Meshii, K. Lu^*, Y. Fujiwara, Extended investigation of the test specimen thickness (TST) effect on the fracture toughness (Jc) of a material in the ductile-to-brittle transition temperature region as a difference in the crack tip constraint- What is the loss of constraint in the TST effects on Jc? Engineering Fracture Mechanics, 135 (2015), 286-294.

6. K. Lu^*, T. Meshii, A systematic investigation of T-stresses for a variety of center-cracked tension specimens, Theoretical and Applied Fracture Mechanics, 77 (2015), 74-81.

Award：

2022  “Minjiang Scholars” Program of Fujian Province

2019 JSME, Excellent Paper in ICONE27

2017  JAEA, R&D Achievements Award

2015  University of Fukui, Outstanding Achievement Award

2012  ASME PVP2012, Finalist paper