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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.

Yuan K.,Shanghai JiaoTong University | Guo D.Q.,China Nuclear Power Design Company | Tong L.L.,Shanghai JiaoTong University | Cao X.W.,Shanghai JiaoTong University
Progress in Nuclear Energy | Year: 2014

Containment would be suffered by over-pressurization if passive containment cooling system (PCS) is failed to remove the heat for the advanced passive pressurized water reactor (PWR). Containment depressurization should be evaluated. Severe accident sequence induced by large break loss of coolant accident (LB-LOCA) at belt of vessel is selected to evaluate the effectiveness of containment venting strategy for advanced passive PWR with the integral safety analyses code, focusing on containment behaviors. Different sizes of the venting path and different open/close pressures of venting are investigated to evaluate CsI mass fraction released to the environment through Containment Air Filtration System (VFS). The results show that depressurization strategy by using the path of VFS can mitigate the high pressure risks and prevent the containment failure when PCS can't be initiated. High pressure at start of venting would reduce the operation times for operator to open the VFS path, reduce the radioactive released to the environment and delay the release time. The Containment Filtered Venting System (CFVS) used in generation II PWR can maintain the containment pressure below the design pressure and reduce the radioactive release for the advanced passive PWR. However much more steam is generated by In-Vessel Retention (IVR) measure, the venting capability is not enough to make the pressure at low value and the venting path should be enlarged. © 2014 Elsevier Ltd. All rights reserved.

Xia B.,Sun Yat Sen University | Li J.,CAS Guangzhou Institute of Geochemistry | Xu L.,Guang Dong Noferrous Metal Engineering Investigation Design Institute | Wang R.,China Nuclear Power Design Company | Yang Z.,Chinese Academy of Geological Sciences
Acta Geologica Sinica | Year: 2011

The Pulan-Xiangquanhe ophiolite in the western Yarlung Tsangpo suture zone of Tibet is investigated for its geochemistry, geochronology, and tectonic implications in detail. Sensitive high resolution ion micro-probe zircon U-Pb dating reveaIs that diabases in the ophiolite from the three locations of Xugugab, Mapam Yum Co and La'nga Co are dated at 122.3±2.5 Ma, 118.8±1.8 Ma and 120.5±1.9 Ma, respectively. These early Cretaceous mafic rocks have Na 20+K 20, rare earth element patterns, trace elemental spider diagram and other geochemical fingerprints of typical mature back-arc basin affinity. Therefore, the Pulan-Xiangquanhe ophiolite formed under a mature back-arc basin enyironment, which was a product of this intra-oceanic subduction system. A suprasubducation system couId have existed in the southern margin of Eurasia, which involved both intra-oceanic and continent-ward subductions. Extension dominated the southern margin of the Eurasian continent during the early Cretaceous.

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.

Li Q.,China Nuclear Power Design Company | Zhang J.,China Nuclear Power Design Company
International Conference on Nuclear Engineering, Proceedings, ICONE | Year: 2013

Two levels of seismic, i.e. OBE and SSE, are conventionally considered in the seismic design of nuclear power plants. OBE is formerly set to equal to one half of SSE. In Advanced Light Water Reacter User Requirements Documents (ALWR-URD), US EPRI recommented to decrease OBE to one third of SSE. In the standard design of third generation of nuclear power plants, such as AP1000 of Westinghouse and EPR of AREVA, OBE was eliminated and substituted by lower level earthquake. In AP1000 standard design, OBE was decreased to one third of SSE and explicit analysis on OBE in the seimic design analyses is not required. Literatures and reports related to the regulatory requirements of seismic design are reviewed to study the reasons and means to be taken to address the issue of elimination of OBE from the design analyses of NPP. It will provide guidelines on the issue of elimination of OBE from seimic analysis of NPP design in China. Copyright © 2013 by ASME.

Wang J.,China Nuclear Power Design Company | Lin M.,China Nuclear Power Design Company
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2016

In the seismic risk analysis for the nuclear power plant, the appropriate data processing method and analytical technique are required. In this study, seismic risk quantification software is developed independently for the first time in China. It uses Monte Carlo sampling method to simulate the seismic frequencies and component conditional failure probabilities, and integrates with accident sequences to assess the plant seismic risk. This method overcomes the shortcomings of the traditional probabilistic risk assessment modelling software in the seismic risk evaluation. Compared with the similar software abroad, this software is more reasonable in the uncertainty process. © 2016, Editorial Board of Journal of Nuclear Power Engineering. All right reserved.

Li X.-H.,China Nuclear Power Design Company | Cao L.-S.,China Nuclear Power Design Company | Nie L.-C.,China Nuclear Power Design Company
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2011

The plastic limit load of pipe elbows, not matter the failure model of the pipe elbows is plastic collapse or elastic-plastic fracture, is one necessary important parameter in the safety assessment. In the design of piping systems for nuclear power stations, the pressure and temperature is the work loads for pipe elbows and also the main loads considered in the structural design of pipe elbows. Assuming the elbow material with ideal elastic-plastic behavior and considering the geometric nonlinearity, the distribution pattern of the plastic limit load in the pipe elbow under high temperature and pressure in the safety injection system is obtained using ANSYS.

Liu Q.,China Nuclear Power Design Company | Chen X.,China Nuclear Power Design Company
Hedongli Gongcheng/Nuclear Power Engineering | Year: 2016

The work of piping layout in the nuclear islands of nuclear power stations includes the pipe and the support designing, which shall satisfy the requirementss of system, vibration, weight and flexibility. This paper have introduced the routing verification program during the basic design in TAISHAN project. The program is implemented in the whole design process, and the result shows that this program can effectively verify the mechanics of the layout of process pipelines, ensure the design quality, reduce the iterative work and improve the efficiency. © 2016, Yuan Zi Neng Chuban She. All right reserved.

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