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Modeling and Measurement of Thermal Properties of Ceramic Composite Fuel for Light Water Reactors

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Pages 357-365 | Published online: 14 Jul 2010

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Wenzhong Zhou, Shripad T. Revankar, Rong Liu & Mehrdad Shahmohammadi Beni. (2018) Microstructure-Based Thermal Conductivity and Thermal Behavior Modeling of Nuclear Fuel UO2-BeO. Heat Transfer Engineering 39:9, pages 760-774.
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Yogesh Madaria, Emadabathuni Anil Kumar, Prakash Maiya & Srikantiah Srinivasa Murthy. (2016) Simulation of Effective Thermal Conductivity of Metal Hydride Packed Beds. Heat Transfer Engineering 37:7-8, pages 616-624.
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Articles from other publishers (28)

Jae Ho Yang, Heung Soo Lee, Dong Seok Kim, Dong-Joo Kim, Ji-Hae Yoon & Yang-Hyun Koo. (2023) Mixed analytical model to estimate the anisotropic effective thermal conductivity and in-reactor performance of metallic microcell UO2. Journal of Nuclear Materials 585, pages 154655.
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Chuanxin Liang, Yunting Su, Mengyuan Hao, Tianjiao Dong, Hengfeng Gong, Wenbo Liu & Dong Wang. (2023) Microstructural evolution of gas bubbles and thermal conductivity in UO2-BeO bicrystal. Journal of Materials Science 58:29, pages 11944-11956.
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Daryn B. Borgekov, Artem L. Kozlovskiy, Maxim V. Zdorovets, Rafael I. Shakirzyanov, Inesh E. Kenzhina & Dmitriy I. Shlimas. (2023) Synthesis and Characterization of the Properties of (1−x)Si3N4-xAl2O3 Ceramics with Variation of the Components. Materials 16:5, pages 1961.
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Wargha Peiman, Igor L. Pioro, Kamiel S. Gabriel & Mohammad Hosseiny. 2023. Handbook of Generation IV Nuclear Reactors. Handbook of Generation IV Nuclear Reactors 613 663 .
Zhanpeng Gong, Zhixuan Xu, Jinlong Hu, Biaojie Yan, Xiangdong Ding, Jun Sun, Pengcheng Zhang & Junkai Deng. (2022) Thermal conductivity prediction of UO2-BeO composite fuels and related decisive features discovery via convolutional neural network. Acta Materialia 240, pages 118352.
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Kai Li, Libo Qian, Xiaojing Li, Yu Ma & Wenzhong Zhou. (2021) BeO Utilization in Reactors for the Improvement of Extreme Reactor Environments - A Review. Frontiers in Energy Research 9.
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Xueyan Zhu, Rui Gao, Hengfeng Gong, Tong Liu, De-Ye Lin & Haifeng Song. (2021) UO2/BeO interfacial thermal resistance and its effect on fuel thermal conductivity. Annals of Nuclear Energy 154, pages 108102.
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Di Yun, Chenyang Lu, Zhangjian Zhou, Yingwei Wu, Wenbo Liu, Shaoqiang Guo, Tan Shi & James F. Stubbins. (2021) Current state and prospect on the development of advanced nuclear fuel system materials: A review. Materials Reports: Energy 1:1, pages 100007.
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Rui Gao, Zhenliang Yang, Bingqing Li, Biaojie Yan, Liang Cheng, Yun Wang, Yi Zhong, Qiqi Huang, Zhiyi Wang, Mingfu Chu, Bin Bai, Xueyan Zhu, Pengcheng Zhang, Rui Li & Tong Liu. (2020) Fabrication of UO2-BeO composite pellets with superior thermal conductivity based on multi-parameter theoretical analyses. Journal of Nuclear Materials 542, pages 152533.
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Yangbin Deng, Bowen Qiu, Bo Pang, Xing Gong, Yingwei Wu, Guanghui Su, Xi Huang, Yongchun Li & Yuan Yin. (2020) Research on performance enhancement of nuclear fuel with SiC cladding by using high thermal conductivity fuels. Progress in Nuclear Energy 124, pages 103330.
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Mitch K. Meyer & Robert C. O’Brien. 2020. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 169 189 .
Fergany Badry, Ryan Brito, M. Gomaa Abdoelatef, Sean McDeavitt & Karim Ahmed. (2019) An Experimentally Validated Mesoscale Model of Thermal Conductivity of a UO2 and BeO Composite Nuclear Fuel. JOM 71:12, pages 4829-4838.
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Wei Zhou & Wenzhong Zhou. (2018) Enhanced thermal conductivity accident tolerant fuels for improved reactor safety – A comprehensive review. Annals of Nuclear Energy 119, pages 66-86.
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Wei Zhou & Wenzhong Zhou. (2018) Thermophysical and Mechanical Analyses of UO2-36.4vol % BeO Fuel Pellets with Zircaloy, SiC, and FeCrAl Claddings. Metals 8:1, pages 65.
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Chad B. Garcia, Ryan A. Brito, Luis H. Ortega, James P. Malone & Sean M. McDeavitt. (2017) Manufacture of a UO2-Based Nuclear Fuel with Improved Thermal Conductivity with the Addition of BeO. Metallurgical and Materials Transactions E 4:2-4, pages 70-76.
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Rong Liu & Wenzhong Zhou. (2017) Multiphysics modeling of novel UO2-BeO sandwich fuel performance in a light water reactor. Annals of Nuclear Energy 109, pages 298-309.
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Kristina Yancey Spencer, Laura Sudderth, Ryan A. Brito, Jordan A. Evans, Clifford S. Hart, Anbang Hu, Andi Jati, Karyn Stern & Sean M. McDeavitt. (2016) Sensitivity study for accident tolerant fuels: Property comparisons and behavior simulations in a simplified PWR to enable ATF development and design. Nuclear Engineering and Design 309, pages 197-212.
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Dominik Naglav, Magnus R. Buchner, Georg Bendt, Florian Kraus & Stephan Schulz. (2016) Off the Beaten Track-A Hitchhiker's Guide to Beryllium Chemistry. Angewandte Chemie International Edition 55:36, pages 10562-10576.
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Dominik Naglav, Magnus R. Buchner, Georg Bendt, Florian Kraus & Stephan Schulz. (2016) Auf neuen Pfaden - per Anhalter durch die Berylliumchemie. Angewandte Chemie 128:36, pages 10718-10733.
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Rong Liu, Andrew Prudil, Wenzhong Zhou & Paul K. Chan. (2016) Multiphysics coupled modeling of light water reactor fuel performance. Progress in Nuclear Energy 91, pages 38-48.
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Rong Liu, Wenzhong Zhou, Andrew Prudil & Paul K. Chan. (2016) Multiphysics modeling of UO2-SiC composite fuel performance with enhanced thermal and mechanical properties. Applied Thermal Engineering 107, pages 86-100.
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W. Peiman, I.L. Pioro, K. Gabriel & M. Hosseiny. 2016. Handbook of Generation IV Nuclear Reactors. Handbook of Generation IV Nuclear Reactors 583 635 .
R. Liu, W. Zhou, P. Shen, A. Prudil & P.K. Chan. (2015) Fully coupled multiphysics modeling of enhanced thermal conductivity UO 2 –BeO fuel performance in a light water reactor. Nuclear Engineering and Design 295, pages 511-523.
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Deepthi Chandramouli & Shripad T. Revankar. (2014) Development of Thermal Models and Analysis of UO 2 -BeO Fuel during a Loss of Coolant Accident . International Journal of Nuclear Energy 2014, pages 1-9.
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S. Yeo, E. Mckenna, R. Baney, G. Subhash & J. Tulenko. (2013) Enhanced thermal conductivity of uranium dioxide–silicon carbide composite fuel pellets prepared by Spark Plasma Sintering (SPS). Journal of Nuclear Materials 433:1-3, pages 66-73.
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M.K. Meyer. 2012. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials 257 273 .
S.K. Kim, W.I. Ko, H.D. Kim, Shripad T. Revankar, W. Zhou & Daeseong Jo. (2010) Cost–benefit analysis of BeO–UO2 nuclear fuel. Progress in Nuclear Energy 52:8, pages 813-821.
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D.S. Li, H. Garmestani & J. Schwartz. (2009) Modeling thermal conductivity in UO2 with BeO additions as a function of microstructure. Journal of Nuclear Materials 392:1, pages 22-27.
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