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The Influence of Suspension and Deposition on Pool Boiling Heat Transfer of Nanofluids: Experiment and Engineering Model Study

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SSRN 2024年

作者： Peng, Cheng Song, Youya Deng, Jian Wu, Jiang Chen, Helin Liu, Fang College of Energy and Mechanical Engineering Shanghai University of Electric Power Shanghai China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

Applications including heat exchangers, high power electronic components, and nuclear reactors now require heat transfer technologies that can achieve both high efficiency and compact footprints. Because nanofluids have advantageous heat transfer properties, they have a greater potential to replace conventional coolants. However, predicting nanofluid boiling heat transfer is still difficult. In order to compare the coupled effects of suspended and deposited nanoparticles with the single effect of deposited nanoparticles, the researchers conducted boiling heat transfer experiments. The findings demonstrated that suspended nanoparticles made the surface less wettable, while the deposited nanoparticles increased the wettability. The number of active nucleate sites and the frequency of bubble detachment increase due to the suspension and deposition of nanoparticles, whereas the diameter of the bubble decreases. Based on the experimental data, predictive models for boiling heat transfer and bubble behavior were proposed, with a range of mass concentrations from 0.001% to 0.005% and heat flux between 60 and 130 kW/m2. Less than 30% was found to be the error margin between the experimental data and the predictive equations. It was discovered that the influence of deposited nanoparticles on boiling heat transfer was usually dominant, according to the predictions made by the proposed theoretical models. © 2024, The Authors. All rights reserved.

关键词： Deposition

High-Order Coupling Method of Reaction Rate-Nuclide Density Used in Kylin-2 Code

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SSRN 2022年

作者： Hu, Yuying Liao, Hongkuan Yao, Dong Yu, Yingrui Zhou, Bingyan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China China

The Projected Prediction-Correction(PPC) method is the most widely used method coupled transport calculation with burnup calculation nowadays, with linear rate(LR) interpolation for normal nuclides and logarithmic linear rate(LLR) interpolation for strong absorbent nuclides. This method has been verified by engineering, and also used in Kylin-2 code. By using PPC method, accurate results could be obtained in the case of detailed division of burnup steps, but the calculation efficiency is not high enough. In this study, the high-order coupling method of reaction rate-nuclide density and its substep calculation method are used to replace the coupling module of Kylin-2 code. By using the high-order coupling and substep calculation to replace parts of transport calculation, the amount of burnup steps is reduced, the calculation time is saved, and the calculation efficiency of Kylin-2 code is improved on the basis of maintaining the whole physical calculation accuracy as much as possible. © 2022, The Authors. All rights reserved.

关键词： Isotopes

Effect of Fission Defects on Tensile Strength of U3si2 Σ5(210) Grain Boundary from First-Principles Calculations

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SSRN 2023年

作者： Zhao, Jiajun Sun, Dan Xi, Liu Chen, Ping Zhao, Jijun Wang, Yuanyuan Dalian University of Technology Liaoning Dalian China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Sichuan Chengdu China

U3Si2 is regarded as a promising accident tolerant fuel (ATF) to replace the commercial fuel UO2;however, U3Si2 grain boundary (GB) embrittlement caused by irradiation-induced defect segregation remains to be clarified. In this work, U3Si2 Σ5(210) symmetrically tilt GB is taken as representative to elucidate the individual effect of xenon (Xe) and vacancy on the tensile strength and failure of GB using first-principles calculations. Compared with the predicted segregation energies of defects at the most energetically favourable positions of GB, Si vacancy (VSi) has much stronger preference to segregate to GB than that of Xe substitution on Si sublattice (XeSi). Moreover, the strengthening/embrittlement potency of GB with single vacancy/Xe is evaluated using the first-principles-based uniaxial tensile test. Although both VSi and XeSi yield a weakening effect on the strength of U3Si2 Σ5(210) GB, such defective GBs exhibit significantly stronger interface strengths compared to the corresponding defects segregated to UO2 Σ3(111) GB. The underlying mechanism of strength change of U3Si2 GB is discussed in terms of charge analysis. Our results can provide fundamental understanding on the mechanical behavior of irradiated GB from an atomic perspective. © 2023, The Authors. All rights reserved.

关键词： Grain boundaries

Effect of AU Ion Irradiation on Microstructure, Mechanical, and Lead-Bismuth Eutectic Corrosion Properties of Zirconia Coatings with Different Y2o3 Content

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SSRN 2024年

作者： Zhu, Changda Qu, Guofeng Zhou, Mingyang Qiu, Xi Gao, Yang Long, Ziyao Yang, Jijun Key Laboratory of Radiation Physics and Technology of Ministry of Education Institute of Nuclear Science and Technology Sichuan University Chengdu610064 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

The yttria-stabilized zirconia (YSZ) coatings with 4 ~ 6 mol.% Y2O3 content was irradiated by 6 MeV Au ions with a fluence 6.0[[EQUATION]]1015 ions/cm2. The cubic to monoclinic transformation of ZrO2 is is identified in the Au-irradiated samples. The cavities are observed in the YSZ layer while larger size cavities are found in the 6YSZ layer. LBE corrosion results show that irradiation improves the adhesion and corrosion resistance of the coating due to the fact that irradiation releases the stresses in the coating. Overall, the 4YSZ coating showed the best corrosion resistance and irradiation resistance in the case of heavy ion irradiation. © 2024, The Authors. All rights reserved.

关键词： Yttria stabilized zirconia

A Study of Flow Measurement Uncertainty Quantification Based on Sample Chunked Bayesian Inference

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SSRN 2024年

作者： Lu, Zihan Zhu, Yudi Zhou, Xinzhi Yu, Junhui Dong, Chenlong Wang, Hailin College of Electronic Information Sichuan University Chengdu610000 China National Key Laboratory of Science and Technology on Reactor System Design Technology Nuclear Power Institute of China Chengdu610213 China

The accuracy of coolant flow measurement of reactor Primary Circuit has a direct impact on the safety and stability of nuclear reactors. However, the presence of errors in the measurement method and instrumentation, as well as the fluid-heat coupling field in the pipeline, leads to a certain degree of uncertainty in the flow measurement. In this paper, an inverse uncertainty quantification method named Sample Chunked Bayesian Inference is proposed based on the establishment of a mathematical model of measurement uncertainty. The proposed method divides the input sample into a number of small samples with single peaks, and then uses each of these as observation sample of Bayesian Inference. The experiments show that the method can effectively quantify the systematic uncertainty and random uncertainty in the measured data. Moreover, compared with the traditional method that use input sample directly as observation sample, the proposed method has higher quantization accuracy. © 2024, The Authors. All rights reserved.

关键词： Bayesian networks

Relaxation and Crystallization of Amorphous Fecraltimo Coatings: Effects on Mechanical Properties and Lead-Bismuth Eutectic Corrosion Resistance

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SSRN 2024年

作者： Yang, Jian Zhou, Mingyang Yang, Jijun Key Laboratory of Radiation Physics and Technology of Ministry of Education Institute of Nuclear Science and Technology Sichuan University Chengdu610064 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

The microstructure evolution of amorphous FeCrAlTiMo coatings during annealing process, and the effects of structural relaxation and crystallization on its mechanical properties and LBE corrosion resistance are systematically investigated. With increasing annealing temperatures, three coatings with different microstructure, including relaxation and crystallization, could be obtained. The structural relaxation is beneficial to improve the LBE corrosion resistance of the coating, but it is accompanied by the loss of mechanical properties (interface bonding strength and wear resistance). The crystalline coating with multi-phase microstructure of BCC, FCC and HCP ( © 2024, The Authors. All rights reserved.

关键词： Corrosion resistance

Optimized Moderator design and Analysis of a Pin-Type Supercritical Carbon Dioxide reactor Based on reactor Monte Carlo Code

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Optimized Moderator Design and Analysis of a Pin-Type Superc...

作者： Zhao, Xingyu Liu, Minyun Cui, Rongyi Huang, Shanfang Wang, Kan Lu, Chuan Department of Engineering Physics Tsinghua University Beijing100084 China Department of Engineering Physics Tsinghua University Beijing100084 China China Nuclear Power Engineering Co. Ltd. Beijing100840 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China

This study analyzed an yttrium hydride (YH2) moderated supercritical carbon dioxide cooled reactor loaded with pin-type, beryllium oxide diluted oxide fuel elements to reduce the critical enrichment. The impact of the YH2 on the coolant void reactivity was studied along with a moderator zoning scheme to flatten the radial power distribution. The YH2 was added as hexagonal moderating rods at the center of the fuel assemblies. The core was modeled using the continuous-energy reactor Monte Carlo code (RMC) with the on-the-fly cross sections treatment. The results showed that the YH2 moderator increased the thermal fission and reduced the critical enrichment of the core with the same diluent volume fraction by more than 30%. The YH2 moderator significantly softened the neutron energy spectrum and reduced the neutron leakage upon core voiding, resulting in both a weaker positive spectral reactivity feedback and a weaker negative leakage reactivity feedback during core depressurization. For an UO2-loaded core, the YH2 gave a lower negative coolant void reactivity, while for a mixed oxide fuel (MOX)-loaded core with diluent volume fractions smaller than 35%, the spectral feedback was more important and the YH2 strongly reduced the positive coolant void reactivity to less than $1. Arranging the YH2 in the peripheral assemblies reduced the radial power peaking factor to 1.319. The study shows that the YH2 moderator can reduce the critical enrichment, make the core less sensitive to voiding, and can flatten the radial power distribution of a single-enrichment core through moderator zoning. [DOI: 10.1115/1.4056772] © 2023 American Society of Mechanical Engineers (ASME). All rights reserved.

关键词： Carbon dioxide

Research on Cylindrical Linear Induction Motor for Drive Mechanism

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Research on Cylindrical Linear Induction Motor for Drive Mec...

International Symposium on Linear Drives for Industry Applications (LDIA)

作者： Xu Niu Tianda Yu Lu Zhang Qingzhao Li Siyu Huang Yanting Liu Hao Wu Yuan Tang School of Electrical Engineering Harbin Institute of Technology Harbin China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

The control rod drive mechanism (CRDM) is a kind of servo mechanism for the reactor control system of the nuclear power plant. This paper presents a cylindrical linear induction motor suitable for the CRDM. First, the structure of the CRDM is introduced. Second, the relationship between the main dimensions and the electromagnetic load is derived. Third, the influence of materials of the mover shielding shell, speed, and electromagnetic parameters on the lifting force is analyzed by the finite-element method (FEM). Meanwhile, the steady-state temperature of each component of the CRDM is obtained. Finally, a scaled-down prototype is manufactured to verify the rationality of the design. The test results show that the FEM results are consistent with the experimental results, and the essential functions such as lifting, lower insertion, and maintenance can be realized.

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Research of the Neutronics Performance Improvement Based on the Small Lead-Based Fast reactor Slbr-50

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SSRN 2022年

作者： Zhao, Chen Lou, Lei Zhang, Bin Zhou, Bingyan Peng, Xingjie Wang, Lianjie Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China

design of high-performance lead-based fast reactor has already become a hotspot in the advanced reactor system. Research of the neutronics performance improvement is presented based on the small lead-based fast reactor SLBR-50. Parameter sensitivity analyses are conducted, including height-diameter ratio(H/D), reflector assembly arrangement, pitch-diameter ratio(P/D) in fuel assembly, fuel material and fuel enrichment partition. Numerical results of eigenvalue in burnup procedure, assembly power distribution and energy spectrum are analyzed. These results provide influences of these design parameters in quantity and the neutronics performance can be improved with parameter optimization. © 2022, The Authors. All rights reserved.

关键词： Fast reactors