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Zou J.,Shanghai JiaoTong University | Guo D.Q.,China Nuclear Power Design Company | Tong L.L.,Shanghai JiaoTong University
Annals of Nuclear Energy | Year: 2015

Severe Accident Management Guidelines (SAMGs) suggests mitigating the consequence of severe accident scenarios by using the non-safety systems if the safety systems are unavailable. For 1000 MWe advanced passive pressurized water reactor (PWR), the normal residual heat removal system (RNS) is proposed to implement the Reactor Coolant System (RCS) injection strategy during severe accidents if safety systems fail. Therefore, evaluation of the effectiveness and negative impact of RNS injection strategy is performed, in which two typical severe accident sequences are selected, which are the typical low-pressure core melt accident sequence induced by Large-break Loss of Coolant Accident (LLOCA) with double-ended guillotine break at cold leg and the typical high-pressure core melt accident induced by Loss of Feed Water (LOFW), to analyze RCS response using the integrated severe accident analysis code. The plant model, including RCS, Engineering Safety Features (ESF), containment and RNS, is built to evaluate the effectiveness of RNS injection by comparing the sequences with and without RCS injection, which shows that RNS injection can terminate core melt progression and maintain core cooling in these accident sequences. However, hydrogen generated during the core reflooding is investigated for the negative impact, which shows that RNS may increase the hydrogen concentration in the containment. For the sequence induced by LOFW, two different RCS depressurization measurements are compared, which shows that opening ADS stages 1-3 valves can cause a rapid increase of hydrogen concentration in the In-containment Refueling Water Storage Tank (IRWST) compartment and may lead to hydrogen detonation risk if hydrogen igniters are unavailable, while hydrogen can be well dispersed into the containment by intentionally opening ADS stage 4 valves, which is suggested as the preferred measure. © 2015 Elsevier Inc. All rights reserved. Source


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. Source


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. Source


Meng X.,Xian Jiaotong University | Bai F.,Xian Jiaotong University | Bai F.,China Nuclear Power Design Company | Yang F.,Xian 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. Source


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. Source

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