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Computational homogenization of thermomechanical properties for Fully Ceramic Microencapsulated fuel with 3D printed SiC matrix

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Annals of Nuclear Energy 2025年 222卷

作者： Chen, Yiwen Lu, Qi Liu, Changwen Li, Wei Zhang, Dalin Su, G.H. State Key Laboratory of Multiphase Flow in Power Engineering Shaanxi Key Laboratory of Advanced Nuclear Energy and Technology School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an710049 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu61213 China State Key Laboratory for Strength and Vibration of Mechanical Structures Xi'an Jiaotong University Xi'an710049 China

Fully Ceramic Microencapsulated (FCM) fuel, fabricated using 3D printing technology, incorporates traditional Tristructural-Isotropic (TRISO) fuel particles embedded within a 3D-printed SiC matrix. This fuel type shows great potential for compact, high-temperature nuclear reactors. However, comprehensive performance analysis remains challenging due to the multilayered structure, complex material properties, and the irradiation behavior of numerous TRISO particles within the matrix. To address these challenges, this study aims to apply finite element (FE)-based computational homogenization to evaluate the fuel's thermomechanical properties. First, a detailed finite element analysis (FEA) of a single TRISO particle's performance was conducted, focusing primarily on the Buffer-IPyC gap size change during irradiation, a critical factor influencing the fuel's thermal performance. Second, the homogenization of a single TRISO particle was performed using FEA, accounting for the changes in the Buffer-IPyC gap size. Finally, homogenized TRISO particles were randomly distributed and perfectly bonded within a 3D-printed SiC matrix to form a Representative Volume Element (RVE). The FE homogenization of the RVE was then conducted to derive the effective thermomechanical properties of the FCM fuel. The packing fraction of TRISO particles in the matrix ranged from 10 % to 50 %, with temperature and burnup conditions spanning 800–1600 K and 0–16 % FIMA, respectively. Results show that irradiation significantly affects the effective properties of the fuel, though this impact diminishes as burnup increases. Additionally, the effective thermal conductivity of the FCM fuel decreases with increasing TRISO packing fraction, assuming the thermal conductivity of the SiC matrix exceeds that of TRISO particles. This study provides a valuable reference for the design and optimization of FCM fuel for future nuclear applications. © 2025 Elsevier Ltd

关键词： Thermal conductivity of solids

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Effective Strengthening and Toughening in High Entropy-Alloy by Combining Extrusion Machining and Heat Treatment

SSRN

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SSRN 2022年

作者： Pu, Zhuo Cai, Songlin L. Dai, Lan-Hong Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610200 China State Key Laboratory of Nonlinear Mechanics Institute of Mechanics Chinese Academy of Sciences Beijing100190 China School of Engineering Science University of Chinese Academy of Sciences Beijing100049 China CAS Center for Excellence in Complex System Mechanics Beijing100190 China China Electric Power Research Institute State Grid Corporation of China Beijing100192 China

This study presents an effective strengthening and toughening approach to improve tensile properties of CrMnFeCoNi high entropy-alloy (HEA) by combining extrusion machining and short-time heat treatment. After such process, preliminary structural heterogeneity has been achieved in this alloy, of which the strength is significantly enhanced while good elongation is retained compared to its homogeneous counterparts. Microstructural characterization reveals varying degrees of partial recrystallization with more or less dislocation density for HEAs under different treatment. It is such structural inhomogeneity that imparts this alloy with good strain hardening ability at high flow stress levels. © 2022, The Authors. All rights reserved.

关键词： Strain hardening

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The statistical analyses on the bubble contact diameters in the vertical narrow channel

The statistical analyses on the bubble contact diameters in ...

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2019 Transactions of the American Nuclear Society, ANS 2019

作者： Lu, Qi Liu, Yu Liu, Wei Chen, Xi He, Hangxing Zhou, Linglan Science and Technology on Reactor System Design Technology Laboratory Chengdu610041 China Nuclear Power Institute of China Chengdu610041 China

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A review and correlations for two phase flow heat transfer in helically coiled tubes 27

A review and correlations for two phase flow heat transfer i...

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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Ma, Haifu Xu, Tao Li, Peiying Gou, Junli Yuan, Hongsheng Chen, Wei Wu, Yirui Zhong, Mingjun Gao, Yingxian Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an710049 China

ISBN: (纸本)9784888983051

Helically coiled heat exchangers have been widely applied in many power conversion systems for their advantages, such as compactness and high efficiency in heat transfer. Reliable heat transfer models are required to analyze the thermal hydraulic characteristics of the once-through helically coiled tube steam generator. The purpose of this study is to evaluate the applicability of the existing heat transfer models. This paper review the experiments for heat transfer in helically coiled tubes in the case of two-phase flow, and summarize and screening corresponding experimental data and correlation. Then, this article compared these correlations to the existing available experimental data to evaluate the applicability of these correlations. Most of the correlations for two phase heat transfer were also valid within the parameter range of pressure, mass flux and heat flux. Results indicate that the currently existing correlation could not accurately match the experiment date. And the Steiner-Taborek correlation was recommended even though the 70% experiment date within the 20% deviation of predicted. Therefore the steam-water two phase flow need to further study to conclude a more suitable correlation in the further. Copyright © 2018-2019 by JSME

关键词： Two phase flow

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Modification of severe accident analysis code for accident tolerant fuel (ATF) applications 27

Modification of severe accident analysis code for accident t...

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27th International Conference on Nuclear Engineering: Nuclear Power Saves the World!, ICONE 2019

作者： Xu, Tao Ma, Haifu Tian, Chao Wu, Yirui Yang, Junyun Wang, Kai Zhang, Bin Wang, Junlong Deng, Yaxin Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu Sichuan China School of Nuclear Science and Technology Xi'an Jiaotong University Xi'an Shaanxi China

ISBN: (纸本)9784888983051

After the Fukushima nuclear accident, we gradually realized the safety issues of the traditional UO2+Zr nuclear fuel system. Accident tolerance fuel (ATF) is a new generation fuel concept proposed to improve the performance of fuel elements against severe accidents, and can withstand the consequences of accidents for a long time while maintaining or improving their performance under normal operating conditions. Nowadays, the issue of the safe utilization of nuclear energy has attracted more and more attention. reactor severe accident simulation and analysis for ATF has also become one of the important research directions. MELCOR is a fully integrated engineering-grade computer code which can model severe accidents phenomena in light water reactors. However, the existing MELCOR code is only applicable for the UO2+Zr fuel system, and cannot simulate the behavior of the ATF. So it is necessary to modify the MELCOR code for ATF applications. Based on extensive investigation, multi-fuel and multi-cladding processing module and new physical properties of ATF are added to MELCOR. Also the heat transfer model, oxidation model and cladding failure model are modified, enabling the MELCOR code to calculate ATF behaviors. Afterwards, the model verification is carried out. Then the traditional UO2+Zr and five ATF combinations are applied to the traditional three-loop PWR nuclear power plant to perform the safety analysis under large break loss of coolant accident (LBLOCA). The calculation results show that ATFs have better accident tolerance ability than UO2+Zr fuel system used in the commercial PWR, and the temperature of the cladding rises more slowly. The cladding failure is also delayed to different extent. The ATF fuel system has a better performance under the severe accident condition. © 2018-2019 by JSME

关键词： Uranium dioxide

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Effect of gamma radiation on the sensing characteristics of FPs and FBGs 27

Effect of gamma radiation on the sensing characteristics of ...

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27th International Conference on Optical Fiber Sensors, OFS 2020

作者： Li, Zhuoyue Xiao, Yaqin Ran, Zengling Yang, Tingting He, Xiu Xiao, Yanbo Shen, Feng Rao, Yunjiang He, Zhengxi Zhu, Jialiang He, Peng Xu, Sijie Chu, Wangwei Zeng, Debiao Fiber Optics Research Center Key Laboratory of Optical Fiber Sensing & Communications Ministry of Education University of Electronic Science & Technology of China Sichuan Chengdu611731 China Center for Optical Fiber Sensing Zhejiang Laboratory Hangzhou310000 China Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu610213 China Chengdu Aircraft Industrial Group Co. Limited 610092 China

The sensing characteristics of Fabry-Perot interferometers (FPIs) and fiber Bragg gratings (FBGs) after irradiation were studied, in which pressure sensitivity of FPI was stable while temperature sensitivity curves of... 详细信息

ISBN: (纸本)9781557523075

关键词： Fiber Bragg gratings

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The SIF model of Zr-4 cladding tube with axial cracks 14

The SIF model of Zr-4 cladding tube with axial cracks

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14th International Nuclear Fuel Cycle Conference, GLOBAL 2019 and Light Water reactor Fuel Performance Conference, TOP FUEL 2019

作者： Chen, L. Liu, L.L. Song, X.M. Pang, H. Xie, X.M. Zeng, X.G. Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China No.328 1st Section of Changshun Avenue Chengdu610213 China Sichuan University No.24 1st South Section of 1st Ring Road Chengdu610021 610213 China

The calculation of the stress intensity factor (SIF) on the axial cracking of the cladding tube is the basis for the study of the failure phenomena of delayed hydride cracking (DHC) and hydrogen embrittlement (HE). In most hydrogen failure models, especially the DHC model, an infinite or semi-infinite plate is used as the modeling basis. There is no doubt that cylindrical shell as a modeling object will make the calculation more accurate for nuclear fuel cladding. This work analyzes the influence of geometric conditions and the external load conditions on SIF of tubular components, respectively, based on virtual crack closure technique (VCCT), using single variable. Then the influence of crack length on SIF is analyzed under concentrated stress loading on the end of Zr-4 cladding tube by numerical analysis method. The approximate calculation formula of the stress intensity factor on the crack front is obtained and verified. Copyright © GLOBAL 2019 - International Nuclear Fuel Cycle Conference and TOP FUEL 2019 - Light Water reactor Fuel Performance *** rights reserved.

关键词： Stress analysis

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Study on numerical model of vortex shedding for three-way pipe 48

Study on numerical model of vortex shedding for three-way pi...

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48th International Congress and Exhibition on Noise Control Engineering, INTER-NOISE 2019 MADRID

作者： Liu, Shuai Feng, ZhiPeng Wu, WanJun Jiang, XiaoZhou Huang, Xuan Qi, HuanHuan Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China. No. 328 Changshun Avenue Shuangliu Chengdu China

ISBN: (纸本)9788487985317

The three-way pipe vortex shedding phenomenon is the main excitation source for pipe vibration, which can lead to the generation of acoustic resonance. The existing researches mainly focus on air and wet steam, however the researches on water medium is rare. In this paper, the formation mechanism of vortex shedding for three-way pipe under water medium is studied, and the influence of turbulence model, water compressibility, boundary layer and model size is discussed. A more accurate simulation model is established, The suggestions for the establishment of the three-way pipe vortex shedding simulation model are given according to the simulation results. © INTER-NOISE 2019 MADRID - 48th International Congress and Exhibition on Noise Control Engineering. All Rights Reserved.

关键词： Vortex shedding

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Study on irradiation hardening of RPV steel based on modified crystal plastic finite element model

Study on irradiation hardening of RPV steel based on modifie...

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2019 Transactions of the American Nuclear Society, ANS 2019

作者： Wang, Xiaotong Yao, Weihua Luo, Ying Dong, Yuanyuan Science and Technology on Reactor System Design Technology Lab Nuclear Power Institute of China Chengdu China Nuclear Power Institute of China Chengdu China

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DC-Side Decoupling Method of DC-link Capacitor Reduction for Single Phase PWM Rectifier

DC-Side Decoupling Method of DC-link Capacitor Reduction for...

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Sustainable Power and Energy Conference (iSPEC)

作者： Jinxin Wang Peng Renyong Kailei Dai Zhiqiang Zhang Ting Zhang Junjie Zhao Qian Chen Jianjian Zhang Science and Technology on Reactor System Design Technology Laboratory Nuclear Power Institute of China Chengdu China Nuclear Power Institute of China Chengdu China

ISBN: (数字)9781728191645

ISBN: (纸本)9781728191652

The integrated charging system of Electric vehicle consists of a single-phase PWM rectifier and a Buck converter. When the single-phase PWM rectifier works with unit power factor, the dc-link voltage contains a large voltage harmonic of twice the grid frequency. Although the output voltage ripple can be controlled within the required range using the proper control of the Buck converter, the second-order harmonic on the dc-link capacitor is inevitable. This paper proposes a de-side decoupling method for the second-order harmonic problem of the dc-link voltage of the integrated charging system. A de-side decoupling half bridge is connected in parallel to absorb the ripple power of twice the grid frequency. This paper analyzes the operating principle of the de-side decoupling half bridge. Based on a theoretical analysis of the topology and the design procedure for controlling system, the proposed converter is designed and simulated. Finally, simulation results are given to verify the method.

关键词： Capacitors Rectifiers Bridge circuits Pulse width modulation Harmonic analysis Control systems Voltage control

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