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Tang B.,China Institute of Technology | Li L.S.,China Institute of Technology | Zhao Y.Y.,China Institute of Technology | Wang L.,China Institute of Technology | Xie C.L.,China Nuclear Power Operation Technology Corporation
Institution of Mechanical Engineers - 7th International Conference on Compressors and Their Systems 2011 | Year: 2011

On the basic principle of stepless capacity control system for large reciprocating compressor, the equations for the process of suction, reflux, compression, discharge and expansion of clearance gas were established. According to these equations, p-V diagrams at various situations were simulated. An experimental platform was setup and the compressor with designed stepless capacity control system run well. The simulated and experimental results show good coincidence and the indicated power of compressor decreases when using the stepless capacity control system. The effects of clearance and valve clearance Mach number on capacity and indicated power, and the relationship between capacity and indicated energy were analyzed. copy; The Authors, 2011.


Wu G.,Hohai University | Ju P.,Hohai University | Song X.,China Electric Power Research Institute | Xie C.,China Nuclear Power Operation Technology Co. | 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.


Han W.,Harbin Engineering University | Chen Q.,China Nuclear Power Operation Technology Corporation | Chen Q.,Nuclear Power Institute of China | Sun Y.,Harbin Engineering University | And 2 more authors.
Metallurgical and Materials Transactions B: Process Metallurgy and Materials Processing Science | Year: 2011

Electrochemical preparation of Mg-Li-Al-La alloys on inert electrodes was investigated in LiCl- KCl melt at 853 K (580 °C). Cyclic voltammograms (CVs) and square wave voltammograms (SWVs) show that the existence of AlCl 3 or AlF 3 could promote La deposition on an active Al substrate, which is predeposited on inert electrodes. All electrochemical tests show that the reduction of La 3+ is a one-step reduction process with three electrons exchanged. The reduction of La(III)→fiLa(0) occurred at -2.04 V, and the underpotential deposition (UPD) of La was detected at -1.55 V (vs Ag/AgCl). The same phenomena concerning La UPD were observed on two inert cathodes, W and Mo. In addition, Mg-Li-Al-La alloys were obtained by galvanostatic electrolysis on the W cathode from La 2O 3 in LiCl-KCl-MgCl 2-KF melts with aluminum as the anode. X-ray diffraction (XRD) measurements indicated that various phases like the Al 2La, Al 12Mg 17, and βLi phase (LiMg/Li 3Mg 7) existed in the Mg-Li-Al-La alloys. The distribution of Mg, Al, and La in Mg-Li-Al-La alloys from the analysis of a scan electron micrograph (SEM) and energy dispersive spectrometry (EDS) indicated that the elements Mg, Al, and La distributed homogeneously in the alloys. © The Minerals, Metals & Materials Society and ASM International 2011.


Ji J.,Anhui University of Science and Technology | Luo C.,Anhui University of Science and Technology | Luo C.,China Nuclear Power Operation Technology Corporation | 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.


Peng X.,Hubei Engineering University | Li X.,Hubei Engineering University | Liu Y.,China Nuclear Power Operation Technology Corporation | 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.


Shi S.,China Nuclear Power Operation Technology Corporation | Shen P.,Nuclear Power Qinshan Co. | Tian X.,China Nuclear Power Operation Technology Corporation | Gao L.,China Nuclear Power Operation Technology Corporation
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.


Hou F.,China Nuclear Power Operation Technology Co.
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.


Zhu X.,China Nuclear Power Operation Technology Corporation | Tian T.,China Nuclear Power Operation Technology Corporation | Zhou L.,China Nuclear Power Operation Technology Corporation | Chen S.,China Nuclear Power Operation Technology Corporation
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2016

AP1000 passive PWR steam generator and main pump is connected by welding, and these welds require in-service inspection. This paper focus on the 3D motion simulation route and its movement algorithm for inspection equipment, based on OpenInventor 3D engine. The developed 3D simulation system realizes the real-time simulation monitoring for the inspection equipment delivery process and working environment, and it has the important practical significance for promoting the intuitive of inspection equipment delivery process and improving the safety of inspection activities. © 2016, Yuan Zi Neng Chuban She. All right reserved.


Chen Y.-Q.,China Nuclear Power Operation Technology Co. | Gui C.,China Nuclear Power Operation Technology Co. | Wang X.-Y.,China Nuclear Power Operation Technology Co. | Liu H.-Y.,China Nuclear Power Operation Technology Co.
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2011

The research investigated on tube fretting due to the outflow and vibration based on hypothesis that the tube can't move to other places. Typical form and layout are considered as analytical objects. In addition, tube fretting due to foreign object is investigated using transient dynamics method according to Archard calculation model. The result shows that lower mass foreign object and foreign object with one end stationary have not remarkably affected on tube integrity under periodic fluctuating load.


Jiang Q.-L.,China Nuclear Power Operation Technology Corporation | Zhou J.-Y.,China Nuclear Power Operation Technology Corporation | Wang X.-Y.,China Nuclear Power Operation Technology Corporation
International Conference on Nuclear Engineering, Proceedings, ICONE | Year: 2013

The turbulence-induced excitation and periodic wake shedding are two important flow-induced vibration mechanisms of tube arrays in steam generators and were normally considered to be random excitation and periodic excitation respectively. Recent findings show that the turbulence-induced excitation is actually the quasi-periodic excitation, which is similar to periodic excitation. Since the turbulence-induced excitation generally occurs in the small pitch-diameter ratio (P/D ratio) tube arrays and the periodic excitation occurs only at large pitch-diameter ratios, the turbulence-induced excitation mechanism seems essentially another form of the periodic excitation at small P/D ratios. To verify this hypothesize and figure out the transition procedure from periodic excitation to quasi-periodic excitation, Numerical simulations were conducted on triangle tube arrays with P/D ratios of 1.47 to 4.0 based on the LES method. Numerical results were compared with experiments results to verify the reliability of numerical models. The lift forces and the force spectra at indifferent P/D ratios were obtained to study the evolution mechanism between turbulence-induced excitation and periodic excitation. The results show that the turbulence-induced excitation and quasi-periodic excitation in tube arrays are essentially other forms of the periodic excitation. The lift forces changed from periodic excitation to quasi-periodic excitation when the P/D ratio was between 2.5 and 3.0, and the lift force nearly complete random excitation when P/D ratios below 1.5. The frequency range of the random excitation is 0 to 50Hz. The peak frequencies of the quasiperiodic excitation were greater than that of periodic excitation and decreased with the increase of P/D ratios. Copyright © 2013 by ASME.

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