Zobrazeno 1 - 10
of 15
pro vyhledávání: '"Shenjie Gu"'
Publikováno v:
Advances in Mechanical Engineering, Vol 9 (2017)
CAP1400 is an advanced large passive nuclear power technology under research and development, and related electromechanical equipment should be improved to guarantee the safety. The driving systems of main steam and feed water isolation valves are el
Externí odkaz:
https://doaj.org/article/d62ddcc8070f42a8820ad57d1a29b278
Publikováno v:
Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues.
In this paper, the mechanical properties of core forgings in Pressurized Water Reactor (PWR )NPPs in China were studied according to different rules of minimum yield strength at room temperature stipulated in ASME codes and RCC-M codes. First, this p
Publikováno v:
Proceedings of the Institution of Mechanical Engineers, Part C: Journal of Mechanical Engineering Science. 232:1069-1078
The driving device of the main steam and feed water isolation valves is one of the most important electromechanical equipment in nuclear power plants, and its motion performances are related to the safety of nuclear power plants. This article propose
Autor:
Zai-Wei Fu, Yuekun Heng, Xiang-Cui Lei, Shangke Pan, Guohao Ren, Fan Yang, Shenjie Gu, Ming Qi
Publikováno v:
Radiation Measurements. 72:39-43
Li6Y(BO3)(3):Ce crystal is a promising type of scintillator for neutron detection. In this study, the properties of Li6Y(BO3)(3):3at%Ce are studied, including its gamma sensitivity, neutron efficiency, alpha/gamma ratio, relative light yield, neutron
Publikováno v:
Advances in Mechanical Engineering, Vol 9 (2017)
CAP1400 is an advanced large passive nuclear power technology under research and development, and related electromechanical equipment should be improved to guarantee the safety. The driving systems of main steam and feed water isolation valves are el
Publikováno v:
Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle and Balance of Plant; I&C, Digital Controls, and Influence of Human Factors.
This article presents the study of the medium block effects on the driving device performances of main steam and feed water isolation valves, which are typical electromechanical equipment in nuclear power plants. The equipment simulation model is est
Publikováno v:
Proceedings of the Institution of Mechanical Engineers, Part C: Journal of Mechanical Engineering Science (Sage Publications, Ltd.); Mar2018, Vol. 232 Issue 6, p1069-1078, 10p
Publikováno v:
Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes.
Based on investigation and analysis of the status of code & standard of China’s nuclear industry, as well as the challenges the industry is facing, a series of suggestions are proposed for the system development, including a hierarchical structure
Publikováno v:
The Proceedings of the International Conference on Nuclear Engineering (ICONE). :ICONE23-1
Publikováno v:
Proceedings of The 20th Pacific Basin Nuclear Conference; 2017, pi-xiv, 14p