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Chen Y.,CAS Institute of Engineering Thermophysics | Chen Y.,University of Chinese Academy of Sciences | Han W.,CAS Institute of Engineering Thermophysics | Sun L.-L.,State Nuclear Power Technology nter | Jin H.-G.,CAS Institute of Engineering Thermophysics
Kung Cheng Je Wu Li Hsueh Pao/Journal of Engineering Thermophysics | Year: 2015

Under the guidance of the principle of energy cascade utilization, this paper proposed a new refrigeration system for low-temperature applications by using mid-temperature sensible heat. Based on the coupling of power and refrigeration cycles, the proposed system comprises a power generation subcycle, an absorption refrigeration subcycle, and a compression refrigeration subcycle. Simulation calculation was conducted, and system's thermodynamic performance was evaluated. The results show that the system's coefficient of performance (COP) reaches 0.277, which is 50% higher than that of the traditional two-stage absorption refrigeration system. The energy saving mechanism was elucidated by exergy analysis and was displayed by t-Q diagrams. The dramatic decrease of exergy destruction in the utilization process of heat source was the main contributor for performance improvement. Moreover, this paper studied the effects of heat source temperature TH and cooling water temperature TCW on the system's performance, providing the guidance for system design. © 2015, Science Press. All right reserved. Source


Deng C.-C.,Huazhong University of Science and Technology | Chang H.-J.,State Nuclear Power Technology nter | Chen L.,State Nuclear Power Technology nter
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2016

The RELAP5 best-estimate code was used to perform small break loss of coolant accident (SBLOCA) for the ACME (advanced core-cooling mechanism experiment) facility built in China. Thereafter, uncertainty quantification evaluation was performed, including the selection of input uncertain parameters, the application of Wilks nonparametric statistics and the calculation of uncertainty propagation based on SNAP interface. Furthermore, the results of uncertainty and sensitivity analysis were discussed. The 95/95 uncertainty bands of key output parameters were obtained, and the lower band of minimum core level is maintained still above the top of the active core section, thus the core uncover does not occur with 95% confidence. Important uncertainty contributors for the minimum core level are identified through sensitivity analysis. © 2016, Editorial Board of Atomic Energy Science and Technology. All right reserved. Source


Chen L.,State Nuclear Power Technology nter | Hu X.,State Nuclear Power Technology nter | Deng C.-C.,Huazhong University of Science and Technology | Huang T.,State Nuclear Power Technology nter
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2016

The application of best estimate plus the uncertainty (BEPU) analysis method becomes trend in the nuclear power plant accident analysis and safety review. The procedure of the statistical BEPU method based on input parameters' propagation was summarized and the key steps were analyzed. The evaluation process can be divided into five major steps: Defining the target parameter(s), identifying important input parameters and their probability distribution, sampling, model analysis and target parameter analysis. It's believed that phenomenon identification and ranking table (PIRT) is a suitable method to identify the important input parameters. The distribution of input parameters is usually obtained from the experimental data or expert judgment. The parametric or nonparametric sampling method can be used to determine the required sampling number, and the later greatly decreases sampling number. Its calculation model should be verified sufficiently to demonstrate its applicability. The statistical results of objective parameter provide uncertainty range and the sensitivity of the input parameters. © 2016, Editorial Board of Atomic Energy Science and Technology. All right reserved. Source


Zhang J.-L.,State Nuclear Power Technology nter | Li P.-F.,State Nuclear Power Technology nter | Chen Y.,State Nuclear Power Technology nter
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2015

The applicability of cold-crucible induction heating technology to the experimental study on the heat transfer characteristics of a molten oxide pool was analyzed in this paper. Then improvements on traditional cold-crucible structure were proposed. The intensity and distribution of internal Joule heat and Lorentz force of the improved cold-crucible were analyzed with numerical simulation method. The analysis results show that the distribution of internal Joule heat is more homogeneous with lower electric power frequency, and the Joule heat amount accounts for a smaller share of the total power, which will be benefit to the heat flux measurement of the side wall of the pool. Besides, when compared with the driving force of natural convection in the pool, the Lorentz force can be ignored, which means the Lorentz force has little impact on the heat transfer and the flow behavior of the molten pool. ©, 2015, Atomic Energy Press. All right reserved. Source


Chen L.,State Nuclear Power Technology nter | Fang F.-F.,State Nuclear Power Technology nter | Deng C.-C.,Tsinghua University | Cui C.-X.,State Nuclear Power Technology nter
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | Year: 2015

The uncertainty evaluation is a key step of best estimate safety analysis for nuclear power plant. The origins of the uncertainty and the uncertainty evaluation methods were described. The methods could be categorized into statistical type and deterministic type, and the general procedure of statistical evaluation method was summarized. Various uncertainty evaluation methods were analyzed and compared from the aspect of computational cost and accuracy. The analysis result shows that the method coupling the nonparametric sampling with a sophisticated high-fidelity thermal-hydraulic model may be the best choice for the uncertainty evaluation in best estimate analysis at present. Under the condition that the “95/95criteria” is satisfied, such a method is easy to implement and the cost is relatively low. ©, 2015, Atomic Energy Press. All right reserved. Source

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