China Nuclear Power Design Company

Shenzhen, China

China Nuclear Power Design Company

Shenzhen, China
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Xie H.,China Nuclear Power Design Company | Yang J.,China Nuclear Power Design Company
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2017

Based on the variation of compression set and service time, the projected seal life of the Lisega large loaded hydraulic snubber uninstalled from McGuire nuclear power station Unit 2 after maintenance free service for over 20 years are calculated. The results show that, taking the large loaded hydraulic snubber provided by Lisega as an example, the projected seal life for external seal and a seal within the fluid boundary is much longer than the replacing cycle for these seals regulated in nuclear power stations in operation or under construction. © 2017, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.


Li J.-Y.,Rensselaer Polytechnic Institute | Liang H.-H.,China Nuclear Power Design Company | He Y.-N.,China Nuclear Power Design Company
Lecture Notes in Electrical Engineering | Year: 2017

Digital control system (DCS) is the central nervous system of automation monitoring and controlling of nuclear power plant. Safe operation and economic benefits of nuclear reactor units depend heavily on the performance of DCS. DCS consists of hardware and control logic. Mal-Operation Rate and Anti-Operation Rate are two important measures to evaluate the reliability of DCS. Failure Mode and Effects Analysis (FMEA) is now in common use to analyze the failures of hardware and control logic. FMEA has been widely used in assessing DCS of nuclear power plant. Fault Tree Analysis (FTA) is effective in analyzing causes and effects of failures. Based on the top-down analyzing strategy, it can easily identify the basic reason accident. Reactor protection system (RPS) is the most important part of DCS, which is used to guarantee the reactor stay in a safety state. This paper takes Spurious Trip Rate of RPS as example, analyzing how different failure modes affect reliability of RPS based on the method of FMEA and FTA. This method can also apply to analyze engineered safety features actuation system (ESFAS), and even the whole DCS of nuclear power plant, which can provide guidance for the design, operation and maintenance of nuclear power plant. © Springer Nature Singapore Pte Ltd. 2017.


Zhang T.,PLA University of Science and Technology | Wu H.,PLA University of Science and Technology | Fang Q.,PLA University of Science and Technology | Huang T.,China Nuclear Power Design Company
Nuclear Engineering and Design | Year: 2017

Since the September 11 attacks, the protective performance of the nuclear power plant (NPP) containment against the impact of large commercial aircraft has been drawing much attention in the field of nuclear security. This paper addresses the numerical simulations of NPP containment subjected to aircraft impact. Firstly, the fine FE models of the Chinese Ling Ao NPP prestressed containment and A320 aircraft are established, and calibrated by the prototype impact test of GE-J79 engine and the modified Riera function, respectively. Then, based on the verified FE models, the entire impact process of the aircraft collision with the containment is reproduced by the missile-target interaction method, which is preferable by comparing with the loading-time history method in analyzing the dynamic responses of the containment. Furthermore, the parametric study is performed to investigate the influences of impact condition (position, angle and velocity) and structural configuration (wall thickness, reinforcement ratio and prestressing force) on the deflection-time history of the NPP containment in the impact central zone. Finally, an explicit formula for predicting the maximum impact deflection of the containment against the aircraft collision is proposed, which is helpful for the engineers in designing the NPP containment. © 2017 Elsevier B.V.


Shang E.-T.,China Nuclear Power Design Company | Liu P.,China Nuclear Power Design Company | Wu S.-J.,China Nuclear Power Design Company
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2017

The integral seismic analysis of reactor head package (RHP) and control rod drive mechanism (CRDM) was performed with simplified three-dimensional finite element model which reflected the collision effects among seismic support plates and between seismic ring and seismic support plates, and the tension-compression nonlinear characteristic of seismic tie rods. Through the nonlinear analysis, the seismic loads necessary for component stress analysis can be derived for each part of RHP and CRDM. Meanwhile, the time-history data of acceleration can be provided for CRDM seismic qualification test. © 2017, Editorial Board of Atomic Energy Science and Technology. All right reserved.


Bai T.,China Nuclear Power Design Company | Chen W.-H.,China Nuclear Power Design Company | Liu Z.,China Nuclear Power Design Company | Gao F.,China Nuclear Power Design Company
Annals of Nuclear Energy | Year: 2017

The software safety of a nuclear digital protection system is critical for the safety of nuclear power plants as any software defect may result in severe damage. In order to ensure the safety and reliability of safety-critical digital system products and their applications, software hazard analysis is required to be performed during the lifecycle of software development. The dynamic software hazard modeling and analysis method based on Colored Petri Net is proposed and applied to the safety-critical control software of the nuclear digital protection system in this paper. The analysis results show that the proposed method can explain the complex interactions between software and hardware and identify the potential common cause failure in software properly and effectively. Moreover, the method can find the dominant software induced hazard to safety control actions, which aids in increasing software quality. © 2017 Elsevier Ltd


Xu D.,China Nuclear Power Design Company | Huang H.,China Nuclear Power Design Company | Bo J.-J.,China Nuclear Power Design Company
Lecture Notes in Electrical Engineering | Year: 2017

Hydrogen waste gas has been produced during normal operation of pressurized water reactor nuclear power plant and sent to the atmospheric environment after treatment in confined space areas. In this process, hydrogen explosive atmosphere is formed and it becomes a threat to the production safety. This article analyzed the potential release resource and explosive environment in the wastes treatment buildings, and presented a few of I&C explosion proof techniques applicable to the nuclear power plant. Commonly used explosion proof techniques of I&C design include flameproof enclosure type and intrinsically safe type. Flameproof enclosure technique focuses on the integrity while intrinsically safe technique emphasizes the compatibility of equipment installation environment and all the apparatuses in the system. The analyses show that the explosive gas atmosphere can be classified as secondary zone and application of different explosion proof techniques should take consideration of different aspects. © Springer Nature Singapore Pte Ltd. 2017.


Xi C.-H.,China Nuclear Power Design Company | Zhang L.-Q.,China Nuclear Power Design Company | Tian Y.,China Nuclear Power Design Company
Lecture Notes in Electrical Engineering | Year: 2017

As digital technology is more and more used in nuclear power plants, the electromagnetic compatibility issues between new digital device and the plant environment are increasingly prominent. This paper is aiming at the dither of control valve in pressurized water reactor project, which is causing by the electromagnetic compatibility issues. And this paper mainly describes the experience of working process and the solving program of failure eliminating. First it introduces the installation condition and operating principle of the valve, then it analyzes the possible causes by using fault tree and find the root cause by site investigation. The root cause of the malfunction is that the feedback signal of valve position is disturbed by an interferential signal about 32 kHz. At last, this paper provides two kinds of program to solve the problem, one is grounding directly and another is grounding with capacitance. © Springer Nature Singapore Pte Ltd. 2017.


Meng X.,Xi'an Jiaotong University | Bai F.,Xi'an Jiaotong University | Bai F.,China Nuclear Power Design Company | Yang F.,Xi'an Jiaotong University | And 2 more authors.
International Journal of Hydrogen Energy | Year: 2010

The traditional cold energy utilization of the liquefied natural gas system needs a higher temperature heat source to improve exergy efficiency, which barricades the application of the common low quality thermal energy. The adoption of a metal hydride heat pump system powered by low quality energy could provide the necessary high temperature heat and reduce the overall energy consumption. Thus, an LNG cold energy recovery system integrating metal hydride heat pump was proposed, and the exergy analysis method was applied to study the case. The performance of the proposed integration system was evaluated. Moreover, some key factors were also theoretically investigated about their influences on the system performance. According to the results of the analysis, some optimization directions of the integrated system were also pointed out. © 2010 Professor T. Nejat Veziroglu. Published by Elsevier Ltd. All rights reserved.


Sun X.-D.,China Nuclear Power Design Company
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2014

The coordinated instrumentation control and protection technology between reactor and steam turbine generator (TG) usually is very significant and complicated for a new construction of nuclear power plant, because it carries the safety, economy and availability of nuclear power plant. Based on successful practice of a nuclear power plant, the experience on interface design and hardware architecture of coordinated intrumentation control and protection technology between reactor and steam turbine generator was abstracted and researched. In this paper, the key points and engineering experience were introduced to give the helpful instructions for the new project. ©, 2014, Atomic Energy Press. All right reserved.


Xu X.-Z.,China Nuclear Power Design Company
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2014

Design change can be reduced and cost of project can be controlled by using configuration management (CM). In this paper, the confirmations of the configuration item and the configuration baseline were discussed in detail. And a good foundation is built for the utility of CM. ©, 2014, Atomic Energy Press. All right reserved.

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