检索结果-内蒙古大学图书馆

SSRN 2024年

作者： Tang, Songsheng Guo, Kailun Tian, Zhixing Wang, Mingjun Wang, Chenglong He, Xiaoqiang Su, Guanghui Qiu, Suizheng Tian, Wenxi School of Nuclear Science and Technology State Key Lab. of Multiphase Flow in Power Engineering Shaanxi Key Lab. of Advanced Nuclear Energy and Technology Xi’an Jiaotong University Shaanxi Xi’an710049 China Key Lab. of Nuclear Reactor System Design Technology China Nuclear Power Research and Design Institute Chengdu610213 China

The spreading and evaporation of sodium droplets is one of the fundamental phenomena in high-temperature heat pipes. The LBM sodium two-phase flow and phase transition model, which can simulate a huge liquid-vapor density ratio, is first established and validated. Then, the spreading and evaporation processes of sodium droplets on solid walls with different wettability are numerically simulated and analyzed. The main conclusions obtained are as follows: (1) The dimensionless spreading diameter and time of the droplet spreading process conforms to Tanner's power law, and the power exponent has exponential relationship with the equilibrium wetting angle;(2) The maximum dimensionless spreading diameter is negatively and linearly correlated with the equilibrium wetting angle;(3) Evaporation of sodium droplets under constant heat flow conditions shows a mixed pattern. The droplets will be detached from the droplet wall at the late stage of evaporation, and the larger the equilibrium wetting angle the sooner the droplets detach. © 2024, The Authors. All rights reserved.

关键词： Evaporation

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Characterization of High-Performance Nanostructured Wick for Heat Pipes

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SSRN 2023年

作者： Sun, Qishi Han, Ruiyu Guo, Kailun Wang, Chenglong Zhang, Jing He, Xiaoqiang Qiu, Suizheng Su, Guanghui Tian, Wenxi Department of Nuclear Science and Technology State Key Lab. of Multiphase Flow in Power Engineering Shaanxi Key Lab. of Advanced Nuclear Energy and Technology Xi’an Jiaotong University Xi’an710049 China Key Lab. of Nuclear Reactor System Design Technology China Nuclear Power Research and Design Institute Chengdu610213 China

To investigate the best performance wick forms to support the design and fabrication of high-performance heat pipes, in this paper, two kinds of nanostructured wick were prepared by the oxidation-reduction method. The effect of surface nanostructure on the wick performance was investigated by comparing the surface characteristics, capillary properties, permeability, and evaporation properties. The result shows that the nanostructured wick presented excellent super hydrophilic properties. A liquid-lift visualization experimental method for measuring the capillary performance factor M was proposed, and it was verified to be correct by the separation effect of the capillary pumping experiment under a vacuum environment. With the increasing oxidized degree, the densification of nanoparticles on the wick surface increased the capillary performance factor M from 8.68 μm to 13.81 μm, with a maximum enhancement of 59.1%. The effective capillary radius decreased from 4.70×10-5 m to 4.01×10-5 m, with a maximum reduction of 14.9%. The permeability increased from 4.33×10-10 m2 to 5.83×10-10 m2, with a maximum enhancement of 34.7%. The increase in porosity made the effective capillary radius dominate the competition for permeability, and the capillary performance factor decreased by 17.1%. The thermal resistance of the wick decreased with the enhancement of the capillary performance factor, which fell from 2.03×10-3 m2·K/W to 1.26×10-3 m2·K/W. The current study provides a reference for the future design and preparation of high-performance heat pipe wicks. © 2023, The Authors. All rights reserved.

关键词： Heat resistance

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Numerical Study on the Impact Characteristics of a Single Molten Lead Bismuth Droplet on Water

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SSRN 2024年

作者： Lin, Yue Zhang, Dalin Chen, Yutong Zhang, Xisi Deng, Jian Du, Peng Tian, Wenxi Qiu, Suizheng Su, Guanghui Department of Nuclear Science and Technology State Key Lab. of Multiphase Flow in Power Engineering Shaanxi Key Lab. of Advanced Nuclear Energy and Technology Xi’an Jiaotong University No.28 Xianningxilu Beilinqu Shaanxi Xi’an710049 China Institute of Reactor Engineering Technology China Institute of Atomic Energy Beijing102413 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu610213 China

As an important link in the possible occurrence of steam explosions, the interaction between molten materials and coolant is of great significance for safety analysis in severe accidents of nuclear reactors. This study is based on the two-dimensional multiphase and multi-component fluid dynamics code ACENA to model the process of single molten lead bismuth droplet impacting a water tank and obtain the velocity changes of the molten droplet as it moves through the water tank. Furthermore, a sensitivity analysis of relevant factors such as the heat transfer area fraction and drag coefficient of the droplet is carried out. To verify models in ACENA, the computation results are compared to experimental data. It is demonstrated that the overall trend of the velocity curve acquired by the ACENA code during the interaction between a molten lead bismuth droplet and water is consistent with the experimental results. The droplet falling velocity increases with the increase in droplet temperature when the temperature of water is the same, and the droplet falling velocity increases with the increase of water temperature at the same droplet temperature. The simulation results by ACENA code for MFCI are in good agreement with experiments which verifies the accuracy of relevant models in ACENA. It can provide an effective means for safety analysis of nuclear reactors in China. © 2024, The Authors. All rights reserved.

关键词： Drops

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Fluid-structure coupling dynamic characteristic analysis of nuclear reactor pool

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Sichuan Daxue Xuebao (Gongcheng Kexue Ban)/Journal of Sichuan University (Engineering Science Edition) 2010年第SUPPL. 2期42卷 181-184页

作者： Ai, Hong-Lei Zhang, Yi-Xiong National Key Lab. of Reactor System Design Technol. Chengdu 640041 China

In order to understand the sloshing characteristic of the fluid in Nuclear reactor pool and its effect on the dynamic characteristic of the pool, a potential-based fluid formulation was implemented in the fluid-structure coupling dynamic analysis. The calculation scale was reduced to a great extent by using the formulation, which is very important for the dynamic characteristic analysis of some complicated pool in nuclear power plants. The validity and the reliability of the formulation were verified by a numerical example. The compressibility effect of the fluid in container on the sloshing characteristic was also analyzed, and the evidence for compressibility assume of fluid in the further analysis was gotten.

关键词： Lakes

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Structural integrity demonstration of high burnup fuel rod

Structural integrity demonstration of high burnup fuel rod

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Fourteenth International Conference on Nuclear Engineering 2006, ICONE 14

作者： Liu, Tong Song, Danrong Zhao, Hua Wang, Kaiming National Key Lab. of Reactor System Design Technology Nuclear Power Institute of China Erhuan Road Chengdu Sichuan China

ISBN: (纸本)0791837831

This paper introduces the current status and the work has been done for structural integrity demonstration of high bumup fuel in China. The FRAMATOME ANP COCCINEL, FLAMBE and MISTIGRI design codes are used in the structural integrity demonstration of fuel rod. This paper presents the results of structural integrity demonstration of AFA3G fuel rod in GNPS. All the design criterion are *** on CAFA program, the new fuel models are planning to be developed in the near future. Copyright © 2006 by ASME.

关键词： Nuclear fuels

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Economic evaluation of nuclear reactor coupling with seawater desalination facility

Economic evaluation of nuclear reactor coupling with seawate...

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Fourteenth International Conference on Nuclear Engineering 2006, ICONE 14

作者： Song, Danrong Liu, Tong Zhao, Hua National Key Lab. of Reactor System Design Technology Nuclear Power Institute of China Chengdu Sichuan No.25 South Third Sect. Erhuan Rd. China

No abstract availab.e

ISBN: (纸本)0791837831

No abstract availab.e

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MIXED CORE AND INCREASING FUEL ENRICHMENT STUDY FOR LING’AO NUCLEAR POWER STATION

MIXED CORE AND INCREASING FUEL ENRICHMENT STUDY FOR LING’AO...

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第十三届国际核工程大会

作者： Dongsheng Li National Key Lab.of Reactor System Design Technology Nuclear Power Institute of China

Ling Ao Nuclear Power Station(LNPS) is a 1,000MWe class of PWR nuclear power station with two *** original reactor core fuel management scheme was designed to use AFA2G fuel assembly,1/3 out-

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