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Wu G.,Hohai University | Ju P.,Hohai University | Song X.,China Electric Power Research Institute | Xie C.,China Nuclear Power Operation Technology Corporation LTD | Zhong W.,China Electric Power Research Institute
Energies | Year: 2016

Nuclear power plants (NPPs) have recently undergone rapid development in China. To improve the performance of both NPPs and grids during adverse conditions, a precise understanding of the coordination between NPPs and grids is required. Therefore, a new mathematical model with reasonable accuracy and reduced computational complexity is developed. This model is applicable to the short, mid, and long-term dynamic simulation of large-scale power systems. The effectiveness of the model is verified by using an actual NPP full-scope simulator as a reference. Based on this model, the interaction and coordination between NPPs and grids under the conditions of over-frequency, under-frequency and under-voltage are analyzed, with special stress applied to the effect of protection systems on the safe operation of both NPPs and power grids. Finally, the coordinated control principles and schemes, together with the recommended protection system values, are proposed for both NPPs and grids. These results show that coordination between the protection systems of NPPs and power networks is a crucial factor in ensuring the safe and stable operation of both NPPs and grids. The results can be used as a reference for coordination between NPPs and grids, as well as for parameter optimization of grid-related generator protection of NPPs. © 2016 by the authors. Source

Hou F.,China Nuclear Power Operation Technology Corporation LTD
International Conference on Nuclear Engineering, Proceedings, ICONE | Year: 2013

Depend on the development of technology, the interaction products have been gradually applied into public awareness in the part of Nuclear Safety. Therefore how to put the information about Nuclear Safety into entertainment produces become a crucial research direction in related industry. The study is to investigate current interaction products based on collection of related information in order to find valuable results for effective propaganda on Nuclear Safety. After the nuclear accident happened in Japan, the popular distrust of Nuclear Energy is spreading all over the world. Due to the kind of negative voices from public in China, several Nuclear constructions have been suspended. Consequently public awareness on Nuclear Safety is supposed to gain more attention for developing Nuclear energy. According to the investigation on current products on Nuclear Safety, the most of exhibited products are unattractive. How to integrate knowledge of Nuclear Safety into interactive technology becomes a key question. The interaction products need to be improved by designing, developing and manufacture. As a result of complex production process, one interaction product needs interdisciplinary cooperation, so that the future products could become attractively, entertainingly, effectively, pertinently from the conclusions of this research. Generally, this study is aim to collect the information of interaction products on Nuclear Safety in the whole world, then investigate and analyze current status using appropriate research method. Finally valuable results might be presented for improving interaction products on Nuclear Safety from the whole production process. Copyright © 2013 by ASME. Source

Peng X.,Hubei Engineering University | Li X.,Hubei Engineering University | Liu Y.,China Nuclear Power Operation Technology Corporation LTD | Zhao Z.,Hubei Engineering University | Ding H.,Hubei Engineering University
Zhongguo Dianji Gongcheng Xuebao/Proceedings of the Chinese Society of Electrical Engineering | Year: 2011

In order to overcome the limitations of magnetism and material of tubes and detect the accumulated oxide at the elbow of high temperature heating surface tubes in supercritical and ultra supercritical thermal power units, an acoustic impulse system was developed which consisted of both software and hardware. According to attenuation coefficient, the characteristic parameter of acoustic signal, the accumulation level of the oxide could be assessed. Experimental results indicate that the increase of the amount of accumulated oxide leads to the increase of attenuation coefficient of acoustic signal resulted from the effect of particle damping. Nondestructive testing of the accumulated oxide can be realized through the extraction and comprehensive analysis of the acoustic signal. © 2011 Chin. Soc. for Elec. Eng. Source

Ji J.,Anhui University of Science and Technology | Luo C.,Anhui University of Science and Technology | Luo C.,China Nuclear Power Operation Technology Corporation LTD | Chow T.,City University of Hong Kong | And 2 more authors.
Energy | Year: 2011

As a modified building-integrated solar thermal system, building-integrated dual-function solar collector here proposed is able to provide passive space heating in cold winter, and water heating in warm seasons. In this study, evaluations were made on this modified collector system for the warm period operation under the water heating mode with natural circulation of flow. A dynamic numerical model has been developed and validated by experimental data. Based on practical air-conditioned room design conditions, numerical analysis was performed to study the water heating performance, as well as to compare the solar transmission through building facade in different seasons with or without its presence. The results show that when working in the water heating mode, the system performs well in providing services hot water in the warm seasons without bringing in summer overheating problem. © 2010 Elsevier Ltd. Source

Shi S.,China Nuclear Power Operation Technology Corporation LTD | Shen P.,Nuclear Power Qinshan Co. | Tian X.,China Nuclear Power Operation Technology Corporation LTD | Gao L.,China Nuclear Power Operation Technology Corporation LTD
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2015

The steam generators tube is a vulnerable part of the primary pressure boundary in nuclear power plants,and its integrity directly affects the safety of NPPs. The tube needs to be plugged when the steam generator (SG) primary side water may leak out to the secondary side because of crack, wear or corrosion of the tube. This paper analyzes a SG tube rolling plug with FEM, simulates and calculates the contact stress between the plug and tube in the process of the rolling plug and after the rolling, to confirm the validity of the plug. The result shows the plug meets the strength requirements. © 2015, Editorial Office of Nuclear Power Engineering. All right reserved. Source

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