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Validation of Lead-Bismuth Thermal Hydraulic Facilities Based on Modified Relap5

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SSRN 2022年

作者： Zhang, Yixin Zhang, Jiaxin Wang, Chenglong Tian, Wenxi Qiu, Suizheng Su, G.H. 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

On the basis of not affecting the original computing power of RELAP5, the physical properties of lead and bismuth are added and verified. The important content of this paper is to use the modified RELAP5 to simulate the transient operating conditions carried out on the three lead-bismuth eutectic experimental devices of NACIE, TALL and NCCL, and compare it with the experimental data. The results show that the temperature error of the heating section of the NACIE facility under transient power conditions is within 7%. The error between the calculated value and the experimental value of the final core temperature under each working condition of the TALL facility is within 5%. The temperature simulation error of the experimental section of the NCCL circular tube heat transfer test is within 4%. The research in this paper can provide data and verification support for the development of the lead-bismuth fast reactor project. © 2022, The Authors. All rights reserved.

关键词： Fast reactors

Numerical Study on Thermal-Hydraulic Characteristics of Lead-Bismuth Loop System Under Moving Conditions

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SSRN 2022年

作者： Yuan, Lanfei Wang, Chenglong Liu, Zhipeng Tian, Wenxi Qiu, Suizheng Su, G.H. 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 Shaanxi Xi'An710049 China

The investigation of flow and heat transfer of lead-bismuth eutectic (LBE) under moving conditions is vital to the design optimization of LBE loop system in offshore engineering. In this paper, the calculation model of lead-bismuth loop system and the calculation method of moving conditions are developed by using commercial CFD software, and experiments were carried out to verify the numerical results. The calculation results demonstrate that the moving conditions will cause periodic fluctuations in the natural circulation flow rate of the loop system. The period of the flow rate fluctuation is consistent with the motion period, and the amplitude of the fluctuation will increase with the increase of the maximum range of motion and the decrease of the motion period. When the maximum heaving amplitude is 0.3m and the period is 8s, the instantaneous fluctuation of the flow rate reaches a maximum of 0.8%, and the reverse flow phenomenon occurs under rolling motion. Rolling and heaving motion also make heat transfer characteristic parameters of the system have periodic instantaneous fluctuation. The maximum instantaneous fluctuation of Nu number reaches 4.63%, and the maximum time average Nu can reach -2.15% under heaving motion of 0.3m-8s. In addition, the influence of rolling on system parameters is more severe than that of heaving. These results obtained in this study have important engineering application value for the design of LBE loop system under moving conditions. © 2022, The Authors. All rights reserved.

关键词： Computational fluid dynamics

Experimental Study on Thermoelectric Characteristics of Heat Pipe Reactor (Nuster-100) Single Assembly

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SSRN 2022年

作者： Yang, Haiwang Wang, Chenglong Tian, Wenxi Qiu, Suizheng Su, Guanghui H. 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 Shaanxi Xi’an710049 China

The heat pipe cooled reactor has the advantages of miniaturization,modularization and high inherent safety,having broad application prospects in the fields of national defense and military,space exploration and energy supply in remote *** this paper, a heat pipe-thermoelectric generator integrated experimental device similar to the heat pipe cooled reactor (NUSTER-100) Single Assembly is *** heat transfer performance of sodium heat pipe and thermoelectric performance of Half-Heusler thermoelectric generator are *** results show that after the sodium heat pipe is started,the axial temperature difference of the heat pipe is 85°C,the equivalent heat transfer coefficient is 40886W/K·m,which can provide stable heat to the thermoelectric *** performance parameters of thermoelectric generator such as open voltage,output power increase with the hot side temperature *** maximum thermoelectric conversion efficiency of single thermoelectric generator reaches 7.2%,but the efficiency of integrated experimental device is only 3.5%. © 2022, The Authors. All rights reserved.

关键词： Heat pipes

Curvature-property coupling governed heat transfer deterioration in supercritical helically coiled tubes: Mechanistic insights and mitigation strategies via structural parametrization

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International Journal of Thermal Sciences 2025年 215卷

作者： Chang, Fucheng Xin, Jiaxing Wu, Xiaoyi Li, Liwei Li, Huixiong Zhu, Yanlin National Key Lab of Aerospace Power System and Plasma Technology School of Mechanical Engineering Xi'an Jiaotong University Xi'an710049 China China Special Equipment Testing and Research Institute Beijing100029 China State Key Laboratory of Multiphase Flow in Power Engineering School of Energy and Power Engineering Xi'an Jiaotong University Xi'an710049 China Shanghai Nuclear Engineering Research & Design Institute Co. Ltd Shanghai200233 China

The unique thermo-hydrodynamic coupling phenomena in the helically coiled tube (HCT) handling supercritical fluids present both opportunities and challenges for next-generation compact heat exchangers. While the pronounced thermophysical property variations near pseudo-critical temperatures (Tpc) and curvature-induced secondary flows synergistically enhance heat transfer coefficient (HTC), their nonlinear coupling mechanisms may unexpectedly provoke severe heat transfer deterioration (HTD). Through systematic numerical investigations, this study reveals that circumferential wall temperature inhomogeneity (CWTI) exhibits an inverted N-shaped evolution, providing valuable insights for thermal homogenization design near Tpc. The secondary flow Reynolds number (Se), quantifying secondary flow intensity, shows a monotonic increase with decreasing coil diameter (Dc) or inner diameter (Di), reaching saturation in high-enthalpy regions. Notably, CWTI demonstrates non-monotonic behavior, achieving minimum values near Tpc before manifesting distinct rebound characteristics near Tpc conditions. Parametric analysis establishes that: (1) Elevating heat flux (q) increases Se, reducing Dc boosts it by 50.3 %, and decreasing Di raises it by 60.0 %. (2) HTD predominantly initiates at the outer wall under high-q conditions, with Dc reduction achieving HTD suppression and 26.9 % enhancement in the local HTC;(3) Reducing the Di results in a reduction of maximum CWTI by 22.5 %–28.6 %, suggesting that structural parametrization effectively mitigates wall temperature non-uniformity, thus suppressing the HTD. While centered on supercritical water, the dimensionless scaling relationships demonstrate extendibility to other media, with the curvature-property coupling mechanism both elucidating fundamental interactions and guiding robust heat exchanger design. © 2025 Elsevier Masson SAS

关键词： Electric heating

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

Non-Hermitian Delocalization in a Two-Dimensional Photonic Quasicrystal

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Physical Review Letters 2024年第26期132卷 263801-263801页

作者： Zhaoyang Zhang Shun Liang Ismaël Septembre Jiawei Yu Yongping Huang Maochang Liu Yanpeng Zhang Min Xiao Guillaume Malpuech Dmitry Solnyshkov Key Laboratory for Physical Electronics and Devices of the Ministry of Education & Shaanxi Key Lab of Information Photonic Technique School of Electronic Science and Engineering Faculty of Electronics and Information PHOTON-N2 Université Clermont Auvergne CNRS Clermont INP F-63000 Clermont-Ferrand France International Research Center for Renewable Energy and State Key Laboratory of Multiphase Flow in Power Engineering Department of Physics National Laboratory of Solid State Microstructures and School of Physics 75231 Paris France

Theoretical and experimental studies suggest that both Hermitian and non-Hermitian quasicrystals show localization due to the fractal spectrum and to the transition to diffusive bands via exceptional points, respectively. Here, we present an experimental study of a dodecagonal photonic quasicrystal based on electromagnetically induced transparency in a Rb vapor cell. First, we observe the suppression of the wave packet expansion in the Hermitian case. We then discover a new regime, where increasing the non-Hermiticity leads to delocalization, demonstrating that the behavior in non-Hermitian quasicrystals is richer than previously thought.

关键词： Electromagnetically induced transparency Localization Photonics Non-Hermitian systems Quasicrystals

Sacos-Plate: A New Thermal-Hydraulic Subchannel Analysis Code for Plate Type Fuel Assemblies

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SSRN 2023年

作者： Sun, Ruiyu Wang, Jianjun Wang, Jinshun Chen, Ronghua Jiang, Xing Tian, Wenxi Qiu, Suizheng Su, Guanghui Gui, Minyang Harbin Engineering University China School of Nuclear Science and Technology Xi’an Jiaotong University Shaanxi Xi’an710049 China Shaanxi Key Lab. of Advanced Nuclear Energy and Technology Xi’an Jiaotong University China State Key Lab. of Multiphase Flow in Power Engineering Xi’an Jiaotong University China Shanghai Nuclear Engineering Research Design Institute Shanghai China

Over the past few decades, plate-type fuel elements have been widely used in advanced research reactors, small modular pressurized water reactors, production reactors, etc., with the advantages of compact structure arrangement, good heat transfer characteristics and high fuel consumption. Currently, a thermal-hydraulic subchannel analysis code, namely SACOS-PLATE code, was newly designed to satisfy the calculation of different types of plate fuel elements under various steady-state operating conditions. Based on the original SACOS code, this updated version modifies the flow distribution model, the plate heat conduction model, the heat distribution model as well as the flow heat transfer model, and then realizes the simulation of the special thermal-hydraulic phenomena of the fuel and the rectangular flow channel. In this present study, the RA-6 experimental data was used to validate the code, and the simulation calculation was performed on the JRR-3 research reactor, which proved the good computing capability of SACOS-PLATE code. © 2023, The Authors. All rights reserved.

关键词： Plates (structural components)

Steady-State Multi-Physics Coupling Analysis of Heat Pipe Cooled Reactor Core

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SSRN 2022年

作者： Zhang, Zhipeng Wang, Chenglong Guo, Kailun Tian, Wenxi Qiu, Suizheng Su, Guanghui Department of Nuclear Science and Technology Shaanxi Key Lab. of Advanced Nuclear Energy and Technology Xi’an Jiaotong University Shaanxi Xi’an710049 China State Key Laboratory of Multiphase Flow in Power Engineering China

Due to the advantages of mobility, safety and universality, the heat pipe reactors have great competitiveness in many applications such as strategic defense locations, remote communities, and emergency locations. In addition, most of the heat pipe reactors are designed as solid-state reactors, which avoid the two-phase flow problem caused by the coolant transformation and make it possible to analyze the reactor with multiple physical field coupling. In this work, a typical heat pipe reactor has been carried out a 3-D neutronic-thermal-mechanical analysis, and steady state analysis is performed by OpenMC coupled with COMSOL. Coupling calculation results show that under normal operation, the maximum temperature and thermal expansion of core is 1338.94 K and 2.53 mm. In the steady-state coupling process, the influence of temperature parameters on physical calculation is mainly reflected in k eff and its power level, the maximum temperature drops from 1347.26 K to 1338.94 K, but it has little influence on power distribution. By coupling calculations, the maximum stress of the reactor is reduced by 5.78 MPa. The research results will support the subsequent development of multi-physics coupled transient analysis code for heat pipe reactors. © 2022, The Authors. All rights reserved.

关键词： Heat pipes

flow Fluctuations and flow Friction Characteristics of Lead-Bismuth Eutectic in a Vertical Tube Under Rolling Conditions

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SSRN 2022年

作者： Liu, Zhipeng Zhao, Yafeng Tian, Wenxi Wang, Chenglong Qiu, Suizheng Su, Guanghui H. School of Nuclear Science and Technology Shaanxi Key Lab. of Advanced Nuclear Energy and Technology Xi’an Jiaotong University Shaanxi Xi’an710049 China State Key Laboratory of Multiphase Flow in Power Engineering China

The effects of rolling motion on the flow characteristics of lead-bismuth eutectic in a vertical circular tube are investigated experimentally. The results show that the pressure drop and flow rate of the forced LBE circulation fluctuate under rolling conditions. The effect of rolling motion on the flow characteristics decreases with the increase of the corresponding static Reynolds number. The rolling motion may increase the time-averaged frictional resistance coefficient of the LBE when flow rate is low. The critical value of the impact Reynolds number is about 125,000. As a result, the time-averaged flow rate decreases. The analysis shows that it is mainly the transverse additional force caused by the rolling motion increases the frictional resistance of the LBE. An empirical correlation is established to predict the frictional resistance coefficient under rolling conditions. This study may be useful in the thermal-hydraulic analysis of LBE as a working fluid under moving conditions. © 2022, The Authors. All rights reserved.

关键词： Reynolds number