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Jiang, Hong

Proceedings of The 20th Pacific Basin Nuclear Conference

Jiang, Hong - Proceedings of The 20th Pacific Basin Nuclear Conference, e-bok

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Table of contents

Part I. Safety and Security

1. 3D Finite Element Analysis for Outlet Nozzle
Rui Liu, Tieping Li

2. A CHF Correlation and Flow Pattern Observation on a Downward-Facing Boiling Surface
Huai-En Hsieh, Mei-Shiue Chen, Yi-Tung Chen, Jyun-Wei Chen, Wei-Keng Lin, Bau-Shei Pei

3. A Mathematical Model to Calculate the Minimum Acceptable Station Blackout Duration Capability of PWR Nuclear Power Plants
Long Sheng, Baozhu Li, Lishan Yao, Xiaoli Yin

4. A Review of Study and Design Improvement of Natural Circulation-Based Heat Removal Systems
Dongqing Wang, Jin Jiang

5. A Seismic Design Method for Safety-Related Instrument Line in ACP1000
Zhiyong Wang, Chungang Niu, Yongjun Li

6. A Simulation-Based Dynamic Approach for External Flooding Analysis in Nuclear Power Plants
Zhegang Ma, Curtis Smith, Steve Prescott

7. Advanced Large PWR LB-LOCA BEPU Analysis with RELAP5-DAKOTA
Xinli Gao, Jianping Jing, Wei Jing, Shaoxin Zhuang, Jieru An

8. An Investigation of FLEX Implementation in Maanshan NPP by Using MAAP 5
Bo-Bin Xiao, Te-Chuan Wang

9. An Overview of Severe Accident Approach at EDF—Contribution of R&D Programs
K. Atkhen, J. Dru, Y. Laroche

10. Analysis and Improvement for External Occupational Expose in Nuclear Power Plants
Zhou Tie-Nan, Huang Hong

11. Analysis and Research of ACP100 Turbine Protection System
Jiansuo Li, Xiaojun Li

12. Analysis of a Severe Accident Initiated By SBLOCA Utilizing MELCOR 2.1 in Gen-III Large PWR
Shi Xingwei, Jing Jianping, Lan Bing, Gao Xinli, Zhang Chunming

13. Analysis of Fuel Rod Behavior Under Steady State and Transient Condition by Modification of THEATRe Code
Amjad Nawaz, Hidekazu Yoshikawa, Ming Yang, Anwar Hussain

14. Analysis of Key Factors for Nuclear Power Plant Emergency
Gao Jianwei, Xue Na, Liu Xinjian, Huang Shuming

15. Analysis of the Effect of the Primary Shield Structures on Dose Rates in the Operating Floor
Yaxiao Wang, Aijun Mi, Yawei Mao, Xiaoxia Wang, Defeng Yang, Yingnan Tian

16. Analysis on the Main Safety Problems of Treatment and Storage Systems of High-Level Liquid Wastes in Nuclear Fuel Reprocessing Plant
Feng-li Song, Dan Lv, Ji Que, Xiao-wei Yang, Shan-gui Zhao, Xin-hua Liu, Hao Wu

17. Annular Flow Interfacial Shear Stress in Pipes
Peng Ju, Yang Liu, Liangming Pan, Mamoru Ishii, Takashi Hibiki, Qinglong Wen, Donghua Lu, Cheng Cheng, Yu Li

18. CANDU-6 Response on Extreme Conditions Combined with SBO, LUHS, and Natural Disasters
S. D. Yi, S. M. Kim, B. J. Moon, S. R. Kim, D. W. Kho

19. Conceptual Design of Integral Test Facility for Hualong One
Congxin Li, Yusheng Liu, Chao Xu, Pan Zhang, Jian Hu, Lijing Wen

20. Consideration on the Usability of Equipment for Severe Accident Conditions
Xinli Yu, Gaopeng Wang

21. Containment Venting During Severe Accident: Reasons and Consequences
Marina Welker, Michael Blase, Carsten Leschke, Junfeng Zhao

22. Sensitivity and Uncertainty Analysis of a SCWR from Monte Carlo Simulations
E. -G. Espinosa–Martínez, C. Martin-del-Campo, J. L. Francois, S. Quezada–García, A. Vázquez-Rodríguez, G. Espinosa-Paredes

23. Design and Research of Nuclear Power Plant Emergency Communication
Wu Yinwei, Li Sheng

24. Design Extension Conditions: Concept and Its Application to Operating Reactor in Canada
Christopher Harwood, Alexandre Viktorov, Quanmin Lei

25. Development and Application of Differential Pressure Protection Device for Classified Pump Inlet Strainer of Pressurized Water Reactor
Qiangtao Li, Haiwei Wan, Xie Geng

26. Development of a Shutdown PSA Model for the TQNPC CANDU Reactor
M. Saint-Denis, X. C. Peng, G. P. Zhang, Y. Cao

27. Development of a Simplified Model for the Passive Containment Cooling System
Meilan Chen

28. Effect of Oxygenation During Cold Shutdown on Source Term for Radiation Shielding Design of RHR System
You Wei, Li Zhuoran, Wang Xiaoxia, Liu Song

29. Experimental and Numerical Simulation Study on Multilayer Cable Trays Fire Under Mechanically Ventilated Conditions
Xianjia Huang, Tianqi Wu, Kun Bi, Xiaoshuang Liu, Xi Jiang

30. Experimental Investigation on the Optimization of ADS Sparger Arrangement in IRWST of AP1000 Plant
Yuhao Zhang, Daogang Lu, Guanghao Wu, Qiong Cao

31. Experimental Study on Heat Transfer Characteristics of Separated Type Heat Pipe
Cheng Cheng, Peng Ju, Qinglong Wen, Donghua Lu, Yu Li, Xiangfei Meng

32. Fire Compartment and Fire Barrier Evaluation in the NPP Fire PSA
Yue Wu

33. Human Reliability Analysis of Nuclear Power Plants Under Fire Scenarios
Yaoyao Zhu, Li Zhang

34. Internal Exposure Study for Nuclear Power Plant Accident and Emergency Conditions
Huang Shuming, Jiang Hua, Xue Na, Liu Xinjian

35. Lessons Learned from Fukushima—Applied to Emergency Preparedness in Taiwan
Chaochun Huang, Juneyuan Huang, Mingte Hsu

36. Localization of the Hot Spots in the Pebble Bed HTR
Leisheng Chen, Wooram Lee, Jaeyoung Lee

37. Management Method for Improving the Ability of Preventing Human Error in Nuclear Power Plant
Mi Na, Wang Quan

38. Modeling Fukushima Dose Consequences with EPZDose
Shaohsuan Chen, Chunkuan Shih, Jongrong Wang

39. Neutron and Gamma-Ray Deep Penetration Shielding Calculation of Lead-Cooled Fast Reactor
Jun Liu, Mei Huang, Kaili Sun, Ran Liu

40. Nuclear and Radiation Accident Emergency Technical Center in China
Yuanyuan Liu, Cai Guo, Ruihuan Liu, Quanyi Lin, Huiguo Yue

41. Numerical Investigation of Passively Cooled Steam Generator Natural Circulation Using RELAP5 Code
Liangguo Li, Qinglong Wen, Xiaohang Wu, Donghua Lu

42. Numerical Simulation of Cavitation Phenomenon in Thin and Long Orifices
Sheng Tianyou, Ma Rubing, Yuan Yidan, Ma Weimin

43. Quantitative Analysis of Safety Margin Reduction of Power Uprate in MBLOCA
Y. M. Chen, M. Lee, J. D. Lin

44. Research and Development of Core Damage Assessment System
Pingting Jiang, Wang Liu

45. Research of Complete Loss of Flow Accident for Hualong One Based on Trace Code
Bin Jia, Jianping Jing, Jinjun Feng, Chunming Zhang, Guohan Chai

46. Research of Testing for Scientific Computing Software in the Area of Nuclear Power Based on Metamorphic Testing
Shiyu Yan, Xiaohua Yang, Meng Li, Hua Liu, Zhaohui Liu

47. Seismic Margin Analysis of In-Service Nuclear Power Plant
Jin-hua Bai, Deng-hua Chen, Yu-chen Jiang, Shuang-wang Zhang, Gui Wang, Dong-mei Wang

48. Research on Severe Accident Management Strategies for CPR1000 NPP Under Refueling Cooling Mode
Pingting Jiang, Dongyu He, Xi Hua, Zhenxun Peng, Juanhua Zhang

49. Research and Application of the Environment Factor of Loss of Offsite Power
Xiaoming Yang, Yang Yang, Rubing Ma

50. Scaling Analysis of Steam Generator During Natural Circulation Phase Under Station Blackout Accident
Pan Zhang, Yu-sheng Liu, Li-jing Wen, Chao Xu, Congxin Li

51. Seismic Margin Assessment of Three Operating Nuclear Power Plants in Taiwan from Regulatory Prospective
Ta-Kang Hsiung, Gung-Min Ho, Ting Chow, Chi-Szu Lee, Shin Chang

52. Selected Containment Systems for Severe Accident Mitigation
Marina Welker, Michael Blase, Carsten Leschke, Junfeng Zhao

53. Severe Accident Progression and Release Categories Analysis in Application to EPZ Evaluation for a BWR-4 NPP
Chen-Yuan Hsia, Jyh-Der Lin

54. Scaling Analysis of Fluid Properties for Natural Circulation Phenomena Under Station Blackout Accident
Yu-sheng Liu, Chao Xu, Cong-xin Li, Pan Zhang, Jian Hu

55. Spent Fuel Cladding Performance Analysis Under Spent Fuel Pool Boiling-off Accident
He Kai, Song Zifan, Zheng Yuntao, Jiang Xiaochuan, Yang Changjiang, Yang Wei

56. Study of Potential for In-Vessel Retention Through External Reactor Vessel Flooding: Code Comparison
Junying Xu, Lei Zhang, Dekui Zhan, Huiyong Zhang, Yahelle Laroche, Hui Guo, Guillaume Niessen

57. Study on Fire Ignition Frequency of Nuclear Power Plant
Yanzhu Chen, Zhichao Yang

58. Study on Human Error Under Digital MCR Environment of Nuclear Power Plant
Yao Jiajun

59. Study on Longitudinal Seismic Response of Underground Gallery Based on ANSYS
Linlin Liu, Xueyan Wang, Zhenxiao Xue

60. Study on New Considerations of Defence in Depth Strategy for Nuclear Power Plants
Wu Yuxiang, Su Jiqiang, Zhang He

61. Technical Insights and Implementation Suggestions for “Practical Elimination of Large Radioactive Release by Design”
Hua Zheng, Shuhong Wei

62. The Analysis of Initiating Events in PSA for TMSR
Jiaxu Zuo, Wei Song, Sen Li, Jinsheng Bi, Jianping Jing

63. The Application of Formal Verification on the FPGA of Instrument and Control Systems in Nuclear Power Plants
Sen Li, Jiaxu Zuo, Hai Zeng

64. The Cyber Security Evaluation of China’s Nuclear Power Plant DCS System
Anyi Yang, Jing Li, Yufang Bian, Xiaofeng Wang

65. Effect of Head Loss on Flow Rate of Spray System and Containment Pressure
Kang-Hau Chiaua, Yung-Shin Tseng, Zhen-Yu Hung, Bau-Shei Pei

66. The Establishment and Simulation of TRACE/FRAPTRAN/MELCOR/SNAP Model for Chinshan Nuclear Power Plant Ultimate Response Guideline
Chunkuan Shih, Jong-Rong Wang, Te-Chuan Wang, Hao-Tzu Lin, Hsiung-Chih Chen, Yu Chiang, Shao-Wen Chen, Show-Chyuan Chiang, Tzu-Yao Yu, Wen-Sheng Hsu

67. The Radiation Protection Cloud Service System in Taiwan
Tzu-Chieh Kuo, Jehn-Ying Huang, Chin-Hsien Tsai

68. The Simulation of Thermal Hydraulic of the Lead-Cooled Fast Reactor
Kaili Sun, Mei Huang, Ran Liu, Jun Liu

69. Uncertainty Study of TMSR-SF Loss of Offsite Power Accident
Kai Wang, Xiaowei Jiao, Shixiang Qu, Zhaozhong He, Kun Chen

Part II. Public Acceptance and Nuclear Education

70. Cultural Factors in Risk Perception: Observations from Interactions with Aboriginal Communities
Danny Mussatti

71. Communication with the Public of the New Nuclear Power Project, Science Popularization in First
Ai-qun Ren

72. Nuclear Power Public Communication and Local Cultural Integration Practice
Wang Nailong, Wang Yidi

73. Strategy on Public Acceptance of Nuclear Power for the Newcomer Countries
Haomiao Lin, Xuefeng Yu

74. The Global Acceptance Proven Model Developed
Bernard Monot

75. The Public Communication
Lin Chang

76. The Public Perception of Risk with Reference to Nuclear Power
Yang Bo

77. To Be a Good Neighbor for the Public
Xiang Chun

Part III. Economics and Reducing Cost

78. A Dissertation on Economic Efficiency of SMR
Hu Jiang, Chen Xiangting

79. Analysis on Engineering Cost Estimation Method for Overseas NPP Projects
Qu Jun, Shi Nan

80. Discussion About Nuclear Power EPC Model
Guo Feng

81. Discussion on Assembly Technology of AP1000 Nuclear Power Plant CA20 Large Structural Module
L. V. Yongfei

82. Earned Value Management for China AP1000/CAP1400 Nuclear Power Plant Construction Projects
Wen Mao

83. Preliminary Study of Technical and Economic Work for Chinese NPP Export Projects
Zheng Baojun, Fa Dan

84. Research on Chinese Nuclear Power Cost Control Under the Perspective of Regulation
De Meng, Wei Zhang, Meng Chang, Ming Yang, Yu Tian

85. Sensitivity Analysis for Cold End System Optimization of a Nuclear Power Plant
Jia Yang, Rongyong Zhang, Wei Bai

86. Shop Drawing Management of Nuclear Power Plant Engineering
Shangrui Chen

87. Study on the Method and Its Application of Performance Evaluation of Nuclear Power Project Construction Based on the Method of Down-Top Resources Collection
Liu Xuejiao

88. The Summary and Research on Nuclear Island Construction and Erection Cost Management of AP1000 Nuclear Power Plant Project
Zhaoyong Yan

89. The Usage and Research of “Potential Trend Notice” in Sanmen AP1000 Nuclear Power Plant Construction Project Change Management
Zhaoyong Yan, Yongzheng Qian

90. The Work Day Determination Method of the New “Nuclear Power Plant Construction Budget Quota” Based on the Work Day of “National General Budget Quota”
Guo Zongzhi, Chen Xiangting

91. To Promote Engineering Surplus Materials Allocation Timely Ratio of Fang Jiashan Project Department
Wang Yiquan, Jin Peng

Nyckelord: Energy, Nuclear Energy, Nuclear Fusion, Nuclear Engineering, Waste Management/Waste Technology

Utgivare
Utgivare
Springer
Utgivningsår
2017
Språk
en
Utgåva
1
Sidantal
14 sidor
Kategori
Teknologi, energi, trafik
Format
E-bok
eISBN (PDF)
9789811023118
Tryckt ISBN
978-981-10-2310-1

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