Nuclear Power Simulation Research Center-Harbin Engineering University

Research Interests：

Advanced simulation technology for nuclear energy、Nuclear Safety and reliability analysis、Nuclear power intelligent operation and maintenance

Publications:

No.	Author	Title	Periodical	Vol.	Page
1	Zhang, Yuandong; Peng, Minjun; Xia Genglei	Numerical investigation on local heat transfer characteristics of S-CO2 in horizontal semicircular microtube	Applied Thermal Engineering	154	380-392
2	Yang, Zhi ; Zhang , Zhang, Zhi-Gang ; Liu, Xing-Chao	Fragmentation of continuous molten copper droplets penetrating into sodium pool	Journal of Nuclear Science and Technology	56	150-159
3	Muhammad Zubair, Zhang Zhijian, and Salah Ud-Din Khan	Calculation and Updating of Reliability Parametersin Probabilistic Safety Assessment	Journal of Fusion Energy	30	13-15
4	Salah Ud-Din Khan；Minjun Peng；Shahab Ud-Din Khan	Neutronics and thermal hydraulic coupling analysis of integrated pressurized water reactor	International Journal of Energy Research	36	15
5	Liu Yongkuo；Li Mengkun；Xie Chunli	Path-planning research in radioactive environment based on particle swarm algorithm	Progress in Nuclear Energy	74	184-192
6	Liu Yongkuo；Xie Chunli；Peng Minjun	Improvement of fault diagnosis efficiency in nuclear power plants using hybrid intelligence approach	Progress in Nuclear Energy	76	122-136
7	Yang Jun；Tunc Aldemir	An algorithm for the computationally efficient deductive implementation of the Markov/Cell-to-Cell-Mapping Technique for risk significant scenario identification	Reliability Engineering & System Safety	145	1-8
8	Zou Bowen ; Yang Ming ; Hidekazu, Yoshikawa	Evaluation of Physical Protection Systems Using an Integrated Platform for Analysis and Design	Transactions on Systems Man Cybernetics-systems	47	2945-2955
9	Zhang, Qian ; Zhao, Qiang ; Zhang, Zhijian	Improvements of the Embedded Self-Shielding Method with Pseudo-Resonant Isotope Model on the Multifuel Lattice System	Nuclear Science and Engineering	192	311-327
10	Gong Meijie；Peng Minjun；Zhu Haishan	Research of multiple refined degree simulating and modeling for high pressure feed water heat exchanger in nuclear power plant	Applied Thermal Engineering	140	190-207
11	Ayodeji, Abiodun ;Liu, Yong-kuo	Support vector ensemble for incipient fault diagnosis in nuclear plant components	Nuclear Engineering and Technology	50	1306-1313
12	Peng, Min-jun; Wang, Hang; Chen, Shan-shan;	An intelligent hybrid methodology of on-line system-level fault diagnosis for nuclear power plant	Nuclear Engineering and Technology	50	396-410
13	Olatubosun, Samuel AbiodunZhang Zhijian	Dependency consideration of passive system reliability by coupled stress-strength interference/functional relations of parameters approach	Reliability Engineering & System Safety	188	549-560
14	Wang Hang；Peng Minjun	A hybrid fault diagnosis methodology with support vector machineand improved particle swarm optimization for nuclear power plants	ISA Transactions	95	358-371
15	Zhang Yuandong；Peng Minjun；Xia Genglei	Numerical investigation on local heat transfer characteristics of S-CO2 in horizontal semicircular microtube	Applied Thermal Engineering	154	380-392
16	Abd El Gawad, K.；Zhang Zhijian	Study on the performance of some non-destructive methods to estimate the uranium enrichment in nuclear materials	Results in Physics	13
17	Chao Nan；Liu Yongkuo	DL-RRT* algorithm for least dose path Re-planning in dynamic radioactive environments	Nuclear Engineering and Technology	51
18	Yang Liqun；Liu Yongkuo；；Peng Minjun	A Fast Gamma-Ray Dose Rate Assessment Method for Complex Geometries Based on Stylized Model Reconstruction	Nuclear Engineering and Technology	51	1436-1443
19	Li Wei；Peng Minjun	Improved PCA method for sensor fault detection and isolation in a nuclear power plant	Nuclear Engineering and Technology	51	146-154
20	Hao Chen；Cheng Youying；Teng Qichen	Quantification and mechanism analysis of the kinf uncertainty propagated from nuclear data for the TRISO particle fuel pebble	Annals of Nuclear Energy	127	248-256
21	Lu Hongxing ; Yang Ming	Reliability modeling by extended GO-FLOW methodology for automatic control component and system at NPP	Nuclear Engineering and Design	342	264-275
22	Sun Lin；Xia Genglei	Analysis of IPWR neutronic-thermohydraulic operation characteristics under low power condition	Annals of Nuclear Energy	129	146-159
23	Yang Liqun；Liu Yongkuo；Peng Minjun	Voxel-based point kernel method for dose rate assessment of non-uniform activity and self-shielding sources in nuclear facility decommissioning	Radiation Physics and Chemistry	164
24	Yang Liqun；Liu Yongkuo；Peng Minjun	A gamma-ray dose rate assessment method for arbitrary shape geometries based on voxelization algorithm	Radiation Physics and Chemistry	158	122-130
25	Jiang Nan；Cong Tenglong	Flow instability analysis of natural circulation under ERVC condition for SMR	Progress in Nuclear Energy	117
26	Ayodeji, Abiodun；Liu Yongkuo	PWR heat exchanger tube defects: Trends, signatures and diagnostic techniques	Progress inNuclear Energy	112	171-184
27	Ha, MM; Guo, ZR; Chen, XL	Evaluation of an emission path length computation model applied at different resolutions in Tomographic Gamma Scanning	Nuclear Instruments & Methods in Physics Research Section a-accelerators Spectrometers Detectors and Associated Equipment	927	267-279
28	Yang, Zhi；Zhang, Zhi-Gang；Liu, Xing-Chao；Ahmed, Rabih	Thermal and hydrodynamic fragmentation of continuous molten copper droplets penetrating into sodium pool	International Communications in Heat and Mass Transfer	56	150-159
29	Saeed, Hanan A.	Online fault monitoring based on deep neural network & sliding window technique	Progress in Nuclear Energy	121
30	Tang, Songsheng	Optimization design for supercritical carbon dioxide compressor based on simulated annealing algorithm	Annals of Nuclear Energy	140
31	Zhang, Yuandong	Performance analysis of S-CO2 recompression Brayton cycle based on turbomachinery detailed design	Nuclear Engineering and Technology	52	2107-2118
32	Xu, Anqi；Zhang, Zhijian；Zhang, Huazhi	Research on Time-Dependent ComponentImportance Measures Considering StateDuration and Common Cause Failure	Frontiers in energyresearch	8
33	Liu, Yong-kuo ; Yang, Li-qun ; Peng, Min-jun	The real-time simulation of exposure dose assessment in radioactive environment based on point-kernel method and human phantom	Radiation Physics and Chemistry	177
34	Chen, Guangliang ; Qian, Hao ;Li, Lei	Design and Analysis of RIF Scheme to Improve the CFD Efficiency of Rod-Type PWR Core	Nuclear Engineering and Technolog	53	3171-3181
35	Sun, Dabin ; Li, Lei ; Tian, Zhaofei	An advanced probability safety margin analysis approach combined deterministic and probabilistic safety assessment	Nuclear Engineering and Design	385
36	Xu, Yifan ; Peng, Minjun ; Xia, Genglei	Optimization of forced circulation to natural circulation transition characteristics of IPWR	Annals of Nuclear Energy	157
37	Wang, Zhichao ; Xia, Hong ; Zhu, Shaomin	Cross-domain fault diagnosis of rotating machinery in nuclear power plant based on improved domain adaptation method	Journal of Nuclear Science and Technology	59	67-77
38	Wang, Zhichao ; Xia, Hong ; Peng, Binsen	A multi-stage hybrid fault diagnosis approach for operating conditions of nuclear power plant	Annals of Nuclear Energy	153

Awards:

No.	Outcome Name	Award	Grade	Award Time
1	NPP Training Simulator	National Science and Technology Progress Award	Second Prize	2007
2	Research on Key Technologies of Operator Support System	Provincial Science and Technology Progress Award	Second Prize	2010
3	Research on Online Simulation Model of Reactor Physics and Thermal Engineering	Provincial Science and Technology Progress Award	Third Prize	2012
4	Nuclear Power Plant Fine Simulation System	Provincial Science and Technology Progress Award	First Prize	2015
5	Research on Experimental Fast Reactor Simulation System	Provincial Science and Technology Progress Award	First Prize	2015
6	Nuclear Power Evaluation Simulation System	Provincial Science and Technology Progress Award	Second Prize	2017
7	Probabilistic Safety Assessment Technology of Nuclear Power Plant	Provincial Science and Technology Progress Award	Third Prize	2017
8	Research on Sodium Fire Mechanism and Protective Measures of Sodium Cooled Fast Reactor	Provincial Science and Technology Progress Award	Third Prize	2018

Contact：

Lei Li

Email：lilei@hrbeu.edu.cn