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2022 29th International Conference on Nuclear Engineering, ICONE 2022

作者： Zhang, Xue Yu, Hongxing Deng, Jian Du, Sijia Zhang, Xilin Zou, Ziqiang Feng, Wenpei Zhang, Yaoxiang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Hefei China

ISBN: (纸本)9780791886434

Liquid metal has the advantages of high boiling point and strong thermal conductivity and is selected as the coolant for a new generation nuclear system. In addition, the narrow rectangular channel is used in the small reactors or research reactors due to its compact structure and high heat transfer capacity. In order to accurately simulate the turbulent heat transfer of liquid metals in narrow rectangular channels, based on the relevant experimental data, this paper explored suitable numerical simulation methods. First of all, according to the research object, the appropriate experimental data was selected, and the geometric modeling, mesh division, and the mesh independence verification were carried out. It was ensured that the y+ meets the requirements of each turbulence model and wall treatment model. Several typical turbulence models and the wall treatment models were evaluated. For the low Prandtl number fluid such as liquid metal, it is necessary to select a suitable turbulent Prandtl number model in the RANS simulation. The sensitivity of the calculation results to the turbulent Prandtl number was analyzed. Finally, the existing turbulent Prandtl number models were evaluated. The suitable at different Pe was given based on experimental value, so that the turbulent heat transfer of liquid metal in a narrow rectangular channel can be accurately simulated. Copyright © 2022 by ASME.

关键词： Liquid metals

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NUMERICAL INVESTIGATION ON DIRECT CONTACT CONDENSATION CHARACTERISTICS OF STEAM INJECTION INTO COLD-WATER PIPE UNDER HEAVING CONDITION 30

NUMERICAL INVESTIGATION ON DIRECT CONTACT CONDENSATION CHARA...

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30th International Conference on Nuclear Engineering, ICONE 2023

作者： Wang, Zhiwei He, Yanping Duan, Zhongdi Huang, Chao Liu, Shiwen State Key Laboratory of Ocean Engineering Shanghai Jiao Tong University Shanghai200240 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

ISBN: (纸本)9784888982566

Direct contact condensation (DCC) is widely appeared in the nuclear power plants and will lead to serious temperature and pressure fluctuations. For ocean nuclear power plants, the DCC is inevitably affected by the sea conditions, such as rolling, heaving motion. In this study, the integration of volume of fluid model (VOF) and condensation model is adopted to simulate the DCC characteristics under heave conditions. The interfacial heat and mass transfer are calculated by user-defined functions (UDF). The additional inertial force method is used to describe the heave motion. First, the DCC numerical model under heave motion is validated by the experimental data, which coincides well with the experiment results. Then, the characteristics of DCC under different heave parameters are numerically studied. The results show that the average condensation rate increases with an increase in heave amplitude, decreases with an increase in heave period. This is mainly because the heave motion will cause the liquid phase to impact the upper pipe wall, and increasing the contact area of vapor and subcooled water. The pressure oscillations induced by DCC are more complicated under heaving conditions. With heave period continuing to change, the formation mechanisms of the pressure peak are different. When the heave period is relatively small, the pressure peak is mainly induced by the acceleration of water phase under high frequency heaving motion. With an increase in the heave period, the heaving motion accelerated the formation of isolated steam bubble, and caused the condensation induced water hammer (CIWH) events, which in turn induced the pressure peak. In addition, the pressure peak is proportional to the heave amplitude. In summary, the direct contact condensation characteristics are more sensitive to the heave period under heaving conditions. These qualitative conclusions may serve as a reference for direct contact condensation simulations under heaving conditions. © 2023 by

关键词： Nuclear power plants

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Emergent antisymmetric wrinkling patterns in films on ridged substrates

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science China(Physics,Mechanics & Astronomy) 2023年第11期66卷 179-187页

作者： Jiahui Zhang Yi Sun Linghui He Yong Ni CAS Key Laboratory of Mechanical Behavior and Design of Materials Department of Modern MechanicsCAS Center for Excellence in Complex System MechanicsUniversity of Science and Technology of ChinaHefei230026China

We report the formation of antisymmetric wrinkling patterns in films on ridged substrates induced by the buckling instability of the substrates via finite element simulations and *** simulated results reveal that the uniaxial compression along the ridge can trigger both the wrinkling instability of the film and the lateral buckling instability of the *** latter could change the wrinkles from a symmetric pattern to an antisymmetric pattern in a range of film-substrate modulus ratio and aspect ratio of the ridge profile,as validated by the experimental observations.A three-dimensional phase diagram with four buckling patterns,i.e.,sole ridge buckling pattern,antisymmetric wrinkling pattern with different wavelengths from ridge buckling,symmetric wrinkling pattern without ridge buckling,and antisymmetric wrinkling pattern with the same wavelength as ridge buckling,is built with respect to the uniaxial compression,modulus ratio,and aspect *** results not only elucidate how and when the interplay between the wrinkling instability and the ridge instability results in the formation of the antisymmetric wrinkling pattern but also offer a way to generate controllable complex wrinkling patterns.

关键词： wrinkling pattern buckling instability ridged film-substrate system antisymmetric wrinkles

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Experimental Study on Aerosol Removal Effected by Spray Characterization 23rd

Experimental Study on Aerosol Removal Effected by Spray Char...

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23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Hu, Peizheng Xu, Zhen Wang, Junlong Tong, Lili Cao, Xuewu School of Mechanical Engineering Shanghai Jiao Tong University Shanghai China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

ISBN: (纸本)9789811988981

The containment spray system is widely used in pressurized water reactor nuclear power plants, which can not only remove the heat in the containment but also remove the fission products suspended in the containment to reduce the discharge of radioactive substances to the environment during accident conditions. The aerosol removal behavior is affected by the spray droplet size distribution. The effect of different spray flow rates on aerosol removal is studied experimentally, and an improved evaluation model is established based on the spray droplet size distribution to analyze the efficiency of removal mechanisms. The experiments are carried out in the CATH (Containment Aerosol Thermal-Hydraulics) test facility with a total volume of 18.5 m3, where aerosols are injected and scrubbed by spray droplets. The spray droplets are generated by a full-cone spray nozzle at the volume flow rate of 0.4 m3/h and 0.6 m3/h, where droplet size distribution is measured by a Laser Diffractometer. Polydisperse particles of TiO2 are used to simulate the solid aerosol, whose diameters are in the range of 0.2 ~ 1.6 μm measured with an Aerosol Spectrometer. Experimental results show that the removal efficiency is higher for the larger particles, and the global removal efficiency of aerosols improved with the increase of spray flow rate from 0.4 to 0.6 m3/h. In addition, the removal efficiency of inertial impaction, interception, Brownian diffusion are quantitatively evaluated by the improved model, which shows that the effect of inertial impaction and interception is more significant for large particles. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Aerosols

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reactor Containment Passive Safety Analysis: Steam Condensation in Presence of Non-condensable Gas Scaled Experiment and Modeling

Reactor Containment Passive Safety Analysis: Steam Condensat...

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2024 Pacific Basin Nuclear Conference, PBNC 2024

作者： Bhowmik, Palash K. Schlegel, Joshua P. Sabharwall, Piyush Division of Reactor System Design and Analysis Idaho National Laboratory Idaho FallsID United States Department of Nuclear Engineering and Radiation Science Missouri University of Science and Technology RollaMO United States

ISBN: (纸本)9798331307653

This study presents steam condensation scaled experiments and semi-empirical models in presence of nitrogen (N)—a noncondensable gas (NCG), simulating air in the reactor containment—to support water-cooled small modular reactors (SMRs) passive containment cooling system (PCCS) design and analysis. Previous experimental studies on PCCS are focused on fixed and smaller tube (mostly 2-in.) geometries and specific test condition variations, bringing challenges with geometric scaling and mismatching with SMR prototypic design. To address these challenges, this study presents steam condensation test dataset obtained from three scaled test sections of 1-, 2-, and 4-in.-diameter steam condensers with an annular/ jacket cooling of 2-, 3-, and 6 in.-diameter tubes, respectively. Test data were collected for steam ranges from 58 to 63 kg/hr., and NCG flow of to 13.3 kg/hr. Annular cooling water flow was varied to obtain required testing conditions of saturated steam 4.4 inlet and fully condensed outlet. Axial temperature test data of bulk cooling water, steam and condensate were collected by thermocouples for three test sections and various steam-NCG mixing/testing conditions. A standard data reduction method was adopted—utilizing iterative and nodalized mass and heat transfer calculation—to estimate axial local heat fluxes, heat transfer coefficients (HTCs), condensation rates, film thickness, and Nusselt number. Based on the obtained dataset semi-empirical model results—a ratio of experimental and Nusselt’s theoretical HTC are presented. Such results and findings are supportive of developing scaled-up testing facility, to model validations and accelerate next generation of reactors development and deployment. © 2024 Pacific Basin Nuclear Conference, PBNC 2024. All rights reserved.

关键词： Thermocouples

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Research and design on the Control Rod Drive Mechanism Power Supply and Control Strategy for the Nuclear Power Plants Based on Silicon-Controlled Rectifier

Research and Design on the Control Rod Drive Mechanism Power...

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International Conference on Power Electronics and Motion Control (IPEMC)

作者： A. Mingzhou Xu B. Gao Zheng C. Zerun Zhao D. Ping Yang E. Yusheng Peng Science and Technology on Reactor System Design Technology Laboratory China Southwest Jiaotong University China

ISBN: (数字)9798350351330

ISBN: (纸本)9798350351347

Due to the characteristics of large output current ripple and long current rise and fall times in the current rod control power supply basedsilicon-controlled rectifier, a decoupling nonlinear adaptive control is *** proposed control strategy can improve the rod control power supply of the speed of respond and the steady-state current accuracy. Practical application has shown that this method solves the output current ripple and the rise and fall time of the current, meeting the working requirements of rod control power supply in nuclear power plants.

关键词： Accuracy Power supplies Conferences Asia Rectifiers Power electronics Steady-state

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Modelling Analysis of Non-uniform Flow and Heat Transfer in Parallel Rectangular Channels During Flow Blockage Condition 23rd

Modelling Analysis of Non-uniform Flow and Heat Transfer in ...

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23rd Pacific Basin Nuclear Conference, PBNC 2022

作者： Chen, Jiayue Chen, Huandong Wang, Xiaoyu Wang, Zefeng Sino-French Institute of Nuclear Engineering and Technology Sun Yat-Sen University Zhuhai610213 China Science and Technology On Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

ISBN: (纸本)9789811987793

In order to establish the non-uniform flow and heat transfer modelling method in parallel rectangular channels, as an additional technique and tool for safety analysis of plate-type fuel, one dimensional two-fluid model coupled with two-dimensional heat conduction of fuel are used to develop a special code for non-uniform flow and heat transfer simulation during flow blockage condition. The flow distribution and fuel temperature field are obtained under different blockage conditions. The two-dimensional heat conduction model are testes under four different power distributions. The simulation results show that mass flow and heat transfer between parallel channels would redistribute after blockage. And the two-dimensional heat conduction model predicted more uniform temperature profile of fuel plate cross-section. Thus, the modelling method used in this paper can be used in the parallel rectangular channels prediction in non-uniformly flow and heat transfer phenomenon. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Two phase flow

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Determining the nuclear temperature dependence on source neutron-proton asymmetry in heavy-ion reactions at intermediate energy

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Chinese Physics C 2023年第5期47卷 152-159页

作者：曲国峰黄宇郑华刘星泉 R.Wada 林炜平黄美容韩纪锋任培培杨振雷张鑫冷强钟 Key Laboratory of Radiation Physics and Technology of the Ministry of Education Sichuan UniversityChengdu 610064China Institute of Nuclear Science and Technology Sichuan UniversityChengdu 610064China School of Physics and Information Technology Shaanxi Normal UniversityXi'an 710119China Cyclotron Institute Texas A&M UniversityCollege StationTexas 77843USA College of Physics and Electronics information Inner Mongolia University for NationalitiesTongliao 028000China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of ChinaChengdu 610213China

In this article,we investigate the dependence of nuclear temperature on emitting source neutron-proton(N/Z)asymmetry with light charged particles(LCPs)and intermediate mass fragments(IMFs)generated from intermediate-velocity sources in thirteen reaction systems with different N/Z asymmetries,^(64)Zn on^(112)Sn,and^(70)Zn,^(64)Ni on^(112,124)Sn,^(58,64)Ni,^(197)Au,and^(232)Th at 40 MeV/*** apparent temperature values of LCPs and IMFs from different systems are deduced from the measured yields using two helium-related and eight carbon-related double isotope ratio thermometers,***,the sequential decay effect on the experimental apparent temperature deduction with the double isotope ratio thermometers is quantitatively corrected explicitly with the aid of the quantum statistical *** present treatment is an improvement compared to our previous studies in which an indirect method was adopted to qualitatively consider the sequential decay effect.A negligible N/Z asymmetry dependence of the real temperature after the correction is quantitatively addressed in heavy-ion reactions at the present intermediate energy,where a change of o.1 units in source N/Z asymmetry corresponds to an absolute change in temperature of an order of 0.03 to 0.29 MeV on average for LCPs and *** conclusion is in close agreement with that inferred qualitatively via the indirect method in our previous studies.

关键词： nuclear temperature N/Z asymmetry dependence Albergo thermometer sequential decay correction heavy-ion reactions at intermediate energy

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Improved vision-only localization method for mobile robots in indoor environments

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Autonomous Intelligent systems 2024年第1期4卷 153-165页

作者： Gang Huang Liangzhu Lu Yifan Zhang Gangfu Cao Zhe Zhou School of Automobile and Traffic Engineering Wuhan University of Science and TechnologyWuhan 430081China Hubei Key Laboratory of Power System Design and Test for Electrical Vehicle Hubei University of Arts and ScienceXiangyang 441053China

To solve the problem of mobile robots needing to adjust their pose for accurate operation after reaching the target point in the indoor environment,a localization method based on scene modeling and recognition has been ***,the offline scene model is created by both handcrafted feature and semantic ***,the scene recognition and location calculation are performed online based on the offline scene *** improve the accuracy of recognition and location calculation,this paper proposes a method that integrates both semantic features matching and handcrafted features *** on the results of scene recognition,the accurate location is obtained through metric calculation with 3D *** experimental results show that the accuracy of scene recognition is over 90%,and the average localization error is less than 1 *** results demonstrate that the localization has a better performance after using the proposed improved method.

关键词： Deep learning Mobile robot Scene recognition Visual localization

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Reliability Analysis of Nuclear Safety-Class DCS ESFAS Based on FTA 7th

Reliability Analysis of Nuclear Safety-Class DCS ESFAS Based...

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7th International Symposium on Digital Instrumentation and Control technology for Nuclear Power Plant, SICPNPP 2023

作者： Zhang, Xu Peng, Hao Feng, Shi-Man Yang, Jing-Hua Chen, Shi-Yong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China PowerChina Sichuan Electric Power Engineering Co. Ltd Chengdu610041 China

ISBN: (纸本)9789819934546

Nuclear safety-class DCS realizes reactor safety protection function, which is directly related to the safe and stable operation of nuclear power plants, so its reliability should be analyzed and optimized. In this paper, the engineered safety features actuation system in nuclear safety-class DCS is analyzed through the control instruction logic flow involved in the structure, according to the components of the series and parallel or voting logic and other logical relations to bulid a fault tree model. Using fault tree model, the reliability degradation trend is obtained, and the minimum cut set, importance degree and other parameters are quantitatively calculated. According to overhaul cycle of nuclear power plant, a maintenance optimization method for engineered safety features actuation system is proposed, and some optimization suggestions are given. © 2023, The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.

关键词： Nuclear power plants

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