Peng, Minjun: search on Z-Library

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1

[IEEE 2006 International Conference on Computational Inteligence for Modelling Control and Automation and International Conference on Intelligent Agents Web Technologies and International Commerce (CIMCA'06) - Sydney, Australia (2006.11.28-2006.12.1)] 2006 International Conference on Computational Inteligence for Modelling Control and Automation and International Conference on Intelligent Agents Web Technologies and International Commerce (CIMCA'06) - A Hybrid Approach for Fault Diagnosis based on Multilevel Flow Models and Artificial Neural Network

Ming, Yang, Jianfei, Li, Minjun, Peng, Shengyuan, Yan, Zhijian, Zhang

Year:

2006

Language:

english

File:

PDF, 242 KB

english, 2006

2

The natural circulation flow characteristic of the core in floating nuclear power plant in rolling motion

Li, Ren, Peng, Minjun, Xia, Genglei, Sun, Lin

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 6.01 MB

english, 2020

3

Calculation analysis on the natural circulation of a passive residual heat removal system for IPWR

Xia, Genglei, Peng, Minjun, Du, Xue

Journal:

Annals of Nuclear Energy

Year:

2014

Language:

english

File:

PDF, 1.92 MB

english, 2014

4

Flow blockage accident or loss of flow accident by using comparative approach of NK/TH coupling codes and RELAP5 code

Khan, Salah Ud-Din, Khan, Shahab Ud-Din, Peng, Minjun

Journal:

Annals of Nuclear Energy

Year:

2014

Language:

english

File:

PDF, 1.33 MB

english, 2014

5

Cause analysis of the fire and explosion during crude oil desulfurization in China

Guo, Song, Peng, Minjun, Ruan, Jifeng, Wan, Wei

Journal:

Journal of Loss Prevention in the Process Industries

Year:

2013

Language:

english

File:

PDF, 1.00 MB

english, 2013

6

Numerical studies of a helical coil once-through steam generator

Xia, Genglei, Yuan, Yuan, Peng, Minjun, Lv, Xing, Sun, Lin

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 827 KB

english, 2017

7

[IEEE 2010 Asia-Pacific Power and Energy Engineering Conference - Chengdu, China (2010.03.28-2010.03.31)] 2010 Asia-Pacific Power and Energy Engineering Conference - Study on Control of Natural Circulation and Forced Circulation in Nuclear Power Plant

Cheng, Shouyu, Peng, Minjun, Tian, Zhaofei, Zhao, Qiang, Xue, Ruojun

Year:

2010

Language:

english

File:

PDF, 403 KB

english, 2010

8

Modification and validation of THEATRe code for the plate type fuel nuclear reactor

Khan, Salah Ud-Din, Peng, Minjun, Li, Lei, Khan, Shahab Ud-Din

Journal:

Annals of Nuclear Energy

Year:

2013

Language:

english

File:

PDF, 1.44 MB

english, 2013

9

[IEEE 2010 Asia-Pacific Power and Energy Engineering Conference - Chengdu, China (2010.03.28-2010.03.31)] 2010 Asia-Pacific Power and Energy Engineering Conference - Research on Digital Control System Simulation for Nuclear Power Plants

Cheng, Shouyu, Peng, Minjun, Gong, Cheng, Zhao, Qiang, Tian, Zhaofei, Zhu, Haishan, Liu, Zhongkun

Year:

2010

Language:

english

File:

PDF, 841 KB

english, 2010

10

Research of flow instability in OTSG under low load conditions

Xia, Genglei, Peng, Minjun, Du, Xue

Journal:

Annals of Nuclear Energy

Year:

2015

Language:

english

File:

PDF, 1.62 MB

english, 2015

11

[ASME 2017 25th International Conference on Nuclear Engineering - Shanghai, China (Sunday 2 July 2017)] Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues - Research on Natural Circulation Flow Characteristics of Floating Nuclear Power Plant in Heaving Motion

Ren, Li, Minjun, Peng, Genglei, Xia, Yanan, Zhao

Year:

2017

Language:

english

File:

PDF, 1.62 MB

english, 2017

12

[IEEE 2010 2nd International Symposium on Information Engineering and Electronic Commerce (IEEC) - Ternopil, Ukraine (2010.07.23-2010.07.25)] 2010 2nd International Symposium on Information Engineering and Electronic Commerce - Design of Thermal Economy On-Line Analysis System of Nuclear Power Unit

Tian, Zhaofei, Peng, Minjun, Wang, Kaichuan

Year:

2010

Language:

english

File:

PDF, 89 KB

english, 2010

13

[IEEE 2010 Asia-Pacific Power and Energy Engineering Conference - Chengdu, China (2010.03.28-2010.03.31)] 2010 Asia-Pacific Power and Energy Engineering Conference - Numerical Simulation Research of Natural Convection Heat Exchanger

Xue, Ruojun, Deng, Chengcheng, Peng, Minjun

Year:

2010

Language:

english

File:

PDF, 392 KB

english, 2010

14

Evaluation of factors influencing the guide to read biomedical English literature course for Chinese new medical postgraduates—a multiple regression analysis

Xu, Zhipeng, Qiu, Jingfan, Yang, Bingya, Huang, Peng, Cai, Lei, Chen, Lin, Hou, Min, Ji, Minjun, Wu, Guanling

Journal:

BMC Medical Education

Year:

2019

Language:

english

File:

PDF, 567 KB

english, 2019

15

Remaining Useful Life Prediction Based on Improved Temporal Convolutional Network for Nuclear Power Plant Valves

Wang, Hang, Peng, Minjun, Xu, Renyi, Ayodeji, Abiodun, Xia, Hong

Journal:

Frontiers in Energy Research

Year:

2020

File:

PDF, 2.15 MB

2020

16

CFD study on the supercritical carbon dioxide cooled pebble bed reactor

Yu, Dali, Peng, Minjun, Wang, Zhongyi

Journal:

Nuclear Engineering and Design

Year:

2015

Language:

english

File:

PDF, 4.15 MB

english, 2015

17

Fault detection, identification and reconstruction of sensors in nuclear power plant with optimized PCA method

Li, Wei, Peng, Minjun, Liu, Yongkuo, Jiang, Nan, Wang, Hang, Duan, Zhiyong

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 4.79 MB

english, 2018

18

Novel fuzzy logic based coordinated control for multi-unit small modular reactor

Zhang, Bowen, Peng, Minjun, Cheng, Shouyu, Sun, Lin

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 1.99 MB

english, 2019

19

Research of multiple refined degree simulating and modeling for high pressure feed water heat exchanger in nuclear power plant

Gong, Meijie, Peng, Minjun, Zhu, Haishan

Journal:

Applied Thermal Engineering

Year:

2018

Language:

english

File:

PDF, 2.01 MB

english, 2018

20

[ASME 2018 26th International Conference on Nuclear Engineering - London, England (Sunday 22 July 2018)] Volume 9: Student Paper Competition - Simulation Research on Thermal-Hydraulic Performance of a Natural Circulation Integrated Pressurized Water Reactor

Zhao, Yanan, Peng, Minjun, Xia, Genglei, Lv, Lianxin

Year:

2018

Language:

english

File:

PDF, 2.14 MB

english, 2018

21

Virus-induced p38 MAPK activation facilitates viral infection

Cheng, Yuting, Sun, Fang, Wang, Luyao, Gao, Minjun, Xie, Youli, Sun, Yu, Liu, Huan, Yuan, Yufeng, Yi, Wei, Huang, Zan, Yan, Huan, Peng, Ke, Wu, Yingliang, Cao, Zhijian

Journal:

Year:

2020

File:

PDF, 3.62 MB

2020

22

Two-step solvothermal synthesis of α-MnS spheres: Growth mechanism and characterization

Xinhua Zhang, Yiqing Chen, Chong Jia, Qingtao Zhou, Yong Su, Bo Peng, Song Yin, Minjun Xin

Journal:

Materials Letters

Year:

2008

Language:

english

File:

PDF, 718 KB

english, 2008

23

Gradient index lens based combined two-photon microscopy and optical coherence tomography

Wang, Taejun, Li, Qingyun, Xiao, Peng, Ahn, Jinhyo, Kim, Young Eun, Park, Youngrong, Kim, Minjun, Song, Miyeoun, Chung, Euiheon, Chung, Wan Kyun, Ahn, G-One, Kim, Sungjee, Kim, Pilhan, Myung, Seung-Ja

Journal:

Year:

2014

Language:

english

File:

PDF, 5.44 MB

english, 2014

24

[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] Volume 2A: Thermal Hydraulics - Analysis of Two-Phase Flow Instability in Multi-Channel System

Xia, Genglei, Peng, Minjun, Xue, Du

Year:

2014

Language:

english

File:

PDF, 1.40 MB

english, 2014

25

[ASME 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference - Anaheim, California, USA (Monday 30 July 2012)] Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems - Thermal-Hydraulic Character Effect Factors Analysis for Passive Residual Heat Removal System of Sodium-Cooled Fast Reactor

Sun, Xiaolong, Peng, Minjun, Xia, Genglei

Year:

2012

Language:

english

File:

PDF, 1.34 MB

english, 2012

26

Uncertainty analysis on natural circulation characteristics under ocean conditions

Wang, Chenyang, Peng, Minjun, Cong, Tenglong, Xia, Genglei

Journal:

Annals of Nuclear Energy

Year:

2019

File:

PDF, 2.29 MB

2019

27

Reliability assessment of passive residual heat removal system of IPWR using Kriging regression model

Wang, Chenyang, Peng, Minjun, Xia, Genglei, Cong, Tenglong

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.67 MB

english, 2019

28

Research of parameter distributing simulation and modeling for the condenser in nuclear power plant

Gong, Meijie, Peng, Minjun, Zhu, Haishan

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.84 MB

english, 2019

29

Optimization design for supercritical carbon dioxide compressor based on simulated annealing algorithm

Tang, Songsheng, Peng, Minjun, Xia, Genglei, Wang, Ge, Zhou, Cheng

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.27 MB

english, 2019

30

Preliminary applications of CFD methodology on analysis of the single-phase laminar natural circulation under swing conditions

Cong, Tenglong, Peng, Minjun, Zhang, Zhijian

Journal:

Progress in Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 3.23 MB

english, 2017

31

[IEEE 2017 25th International Conference on Geoinformatics - Buffalo, NY (2017.8.2-2017.8.4)] 2017 25th International Conference on Geoinformatics - Research of key technology in the construction of geocoding engine

Gao, Shan, Chen, Si, Peng, Minjun, Pan, Chenling

Year:

2017

File:

PDF, 417 KB

2017

32

Evaluation of an emission path length computation model applied at different resolutions in Tomographic Gamma Scanning

Han, Miaomiao, Guo, Zhirong, Liu, Haifeng, Peng, Minjun, Li, Qinghua, Chen, Xianglei

Journal:

Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

Year:

2019

File:

PDF, 2.90 MB

2019

33

Assessment of Severe Accident Management for Small IPWR under an ESBO Scenario

Yu, Hao, Peng, Minjun

Journal:

Science and Technology of Nuclear Installations

Year:

2019

File:

PDF, 4.20 MB

2019

34

[IEEE 2010 Asia-Pacific Power and Energy Engineering Conference - Chengdu, China (2010.03.28-2010.03.31)] 2010 Asia-Pacific Power and Energy Engineering Conference - A Review: Activities in the Field of Small and Medium Sized Nuclear Power Plants

Khan, Salah Ud-din, Peng, Minjun, Liu, Jiange

Year:

2010

Language:

english

File:

PDF, 192 KB

english, 2010

35

[IEEE 2010 Asia-Pacific Power and Energy Engineering Conference - Chengdu, China (2010.03.28-2010.03.31)] 2010 Asia-Pacific Power and Energy Engineering Conference - Simulation Based Multi-experts Evaluation Method for Human-machine Interface Design of Main Control Room

Yan, Shengyuan, Yu, Kun, Zhang, Zhijian, Peng, Minjun

Year:

2010

Language:

english

File:

PDF, 354 KB

english, 2010

36

Identification of Highly Selective Lipoprotein-Associated Phospholipase A2 (Lp-PLA2) Inhibitors by a Covalent-Fragment-Based Approach

Huang, Fubao, Hu, Hangchen, Wang, Kai, Peng, Chengyuan, Xu, Wenwei, Zhang, Yu, Gao, Jing, Liu, Yishen, Zhou, Hu, Huang, Ruimin, Li, Minjun, Shen, Jianhua, Xu, Yechun

Journal:

Journal of Medicinal Chemistry

Year:

2020

File:

PDF, 2.94 MB

2020

37

An evaluation of designed Start-up System (SUS) for once-through steam generators

Yu, Dali, Peng, Minjun, Xia, Genglei, Mao, Wanchao, Yang, Yang

Journal:

Annals of Nuclear Energy

Year:

2014

Language:

english

File:

PDF, 1.75 MB

english, 2014

38

[ASME 17th International Conference on Nuclear Engineering - Brussels, Belgium (July 12–16, 2009)] Volume 4: Codes, Standards, Licensing and Regulatory Issues; Student Paper Competition - Evaluation of the Flow and Heat Transfer Characteristic in Vertical Narrow Annulus Channel Based on the RELAPSCDAPSIM/MOD3.4 Code

Liu, Jiange, Peng, Minjun

Year:

2009

Language:

english

File:

PDF, 239 KB

english, 2009

39

[IEEE 2010 Asia-Pacific Power and Energy Engineering Conference - Chengdu, China (2010.03.28-2010.03.31)] 2010 Asia-Pacific Power and Energy Engineering Conference - Small-Break Loss of Coolant Accident Analysis of the Integrated Pressurized Water Reactor

Liu, Jiange, Peng, Minjun, Zhang, Zhijian, Jiang, Liguo

Year:

2010

Language:

english

File:

PDF, 318 KB

english, 2010

40

Track truncation method for improving the computational efficiency of 2D matrix MOC

Zheng, Yong, Peng, Minjun

Journal:

Annals of Nuclear Energy

Year:

2017

Language:

english

File:

PDF, 1.25 MB

english, 2017

41

Fault detectability analysis in PCA method during condition monitoring of sensors in a nuclear power plant

Li, Wei, Peng, Minjun, Wang, Qingzhong

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 4.70 MB

english, 2018

42

Photoluminescence properties of a single-phase phosphor NaBaPO4:Eu2+, Mn2+ with good thermal stability for white LEDs

Chen, Yan, Cai, Minjun, He, Fuming, Peng, Yifu, Lu, Jintong, Wang, Bo, Chen, Yeqing, Wen, Jinxiu, Liu, Zheng, Zeng, Qingguang, Wang, Jing

Journal:

Journal of Luminescence

Year:

2018

Language:

english

File:

PDF, 1.09 MB

english, 2018

43

Analysis of the transient performance of the flashing-driven natural circulation IPWR

Zhao, Yanan, Peng, Minjun, Xu, Yifan, Xia, Genglei, Wang, Chang

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 1.68 MB

english, 2019

44

[IEEE 2011 Asia-Pacific Power and Energy Engineering Conference (APPEEC) - Wuhan, China (2011.03.25-2011.03.28)] 2011 Asia-Pacific Power and Energy Engineering Conference - Preliminary Assessment of Mean Steam Line Break Accident in an Integral Pressurized Water Reactor(IPWR)

Ud-Din, Khan Salah, Peng, Minjun, Zubair, Muhammad

Year:

2011

Language:

english

File:

PDF, 266 KB

english, 2011

45

[IEEE 2006 International Conference on Computational Inteligence for Modelling Control and Automation and International Conference on Intelligent Agents Web Technologies and International Commerce (CIMCA'06) - Sydney, Australia (2006.11.28-2006.12.1)] 2006 International Conference on Computational Inteligence for Modelling Control and Automation and International Conference on Intelligent Agents Web Technologies and International Commerce (CIMCA'06) - A Subjective Evaluation Method for Human-computer Interaction Interface Design Based on Grey Theory

Shengyuan, Yan, Zhijian, Zhang, Minjun, Peng, Ming, Yang

Year:

2006

Language:

english

File:

PDF, 203 KB

english, 2006

46

Simulation analysis of an open natural circulation for the passive residual heat removal in IPWR

Jiang, Nan, Peng, Minjun, Cong, Tenglong

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 2.82 MB

english, 2018

47

Flashing-driven natural circulation characteristics analysis of a natural circulation integrated pressurized water reactor

Zhao, Yanan, Peng, Minjun, Xia, Genglei, Lv, Lianxin

Journal:

Nuclear Engineering and Design

Year:

2018

Language:

english

File:

PDF, 1.78 MB

english, 2018

48

Effects of interaction models on upward subcooled boiling flow in annulus

Zhang, Xiang, Yu, Ting, Cong, Tenglong, Peng, Minjun

Journal:

Progress in Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 2.00 MB

english, 2018

49

Margin evaluation of in-vessel melt retention for small IPWR

Jiang, Nan, Cong, Tenglong, Peng, Minjun

Journal:

Progress in Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 4.13 MB

english, 2019

50

Research of two-phase flow instability in parallel narrow multi-channel system

Genglei Xia, Minjun Peng, Yun Guo

Journal:

Annals of Nuclear Energy

Year:

2012

Language:

english

File:

PDF, 2.67 MB

english, 2012

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