Citations (62)
Keep up to date with the latest research on this topic with citation updates for this article.
Read on this site (4)
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.
Read now
Read now
Mark R. St J. Foreman. (2018) Reactor accident chemistry an update. Cogent Chemistry 4:1.
Read now
Read now
Jakub Roleček, Štěpán Foral, Karel Katovský & David Salamon. (2017) A feasibility study of using CeO2 as a surrogate material during the investigation of UO2 thermal conductivity enhancement. Advances in Applied Ceramics 116:3, pages 123-131.
Read now
Read now
Ryan Latta, ShripadT. Revankar & AlvinA. Solomon. (2008) Modeling and Measurement of Thermal Properties of Ceramic Composite Fuel for Light Water Reactors. Heat Transfer Engineering 29:4, pages 357-365.
Read now
Read now
Articles from other publishers (58)
Kaiyuan Wang, Yanan Zhu & Xin Jin. 2024. Proceedings of the 2023 Water Reactor Fuel Performance Meeting. Proceedings of the 2023 Water Reactor Fuel Performance Meeting
87
96
.
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.
Crossref
Crossref
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.
Crossref
Crossref
Heung Soo Lee, Dong Seok Kim, Dong-Joo Kim, Jae Ho Yang, Ji-Hae Yoon & Ji Hwan Lee. (2023) Development of thermal conductivity model with use of a thermal resistance circuit for metallic UO2 microcell nuclear fuel pellets. Nuclear Engineering and Technology.
Crossref
Crossref
Bingqing Li, Zhenliang Yang, Zhiyi Wang, Qiqi Huang, Dezhi Zhang, Qingdong Xu, Liang Xie, Yi Zhong, Yun Wang, Limei Duan, Fengyun Hu, Mingfu Chu, Rui Gao, Pengcheng Zhang & Bin Bai. (2023) Thermal conductivity of UO2 pellets enhanced by a semi-continuous structure of Ti3SiC2. Ceramics International 49:13, pages 21737-21744.
Crossref
Crossref
Linu Malakkal, Anil Prasad, Jayangani Ranasinghe, Ericmoore Jossou, Lukas Bichler & Jerzy Szpunar. (2023) Enhanced thermal conductivity of spark plasma-sintered thorium dioxide-silicon carbide composite fuel pellets. Nuclear Engineering and Technology.
Crossref
Crossref
Andrew T. Nelson. (2023) Prospects for additive manufacturing of nuclear fuel forms. Progress in Nuclear Energy 155, pages 104493.
Crossref
Crossref
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
.
Tingting Zou, Wei Gao & Xin Wang. 2023. Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3. Proceedings of the 23rd Pacific Basin Nuclear Conference, Volume 3
147
159
.
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.
Crossref
Crossref
Yang Huang, Nanyan Hu, Yicheng Ye, Zhibing Ou & Xin Shi. (2022) Preparation and pore-forming mechanism of MgO–Al2O3–CaO-based porous ceramics using phosphorus tailings. Ceramics International 48:20, pages 29882-29891.
Crossref
Crossref
Biaojie Yan, Zhiyi Wang, Tao Fa, Liang Cheng & Pengcheng Zhang. (2022) Bi-objective optimization of thermal conductivity and thermal stress of UO2–Mo–Nb composite through Gaussian process regression and NSGA-II method. Ceramics International 48:16, pages 23777-23783.
Crossref
Crossref
Bowen Gong, Erofili Kardoulaki, Kun Yang, Andre Broussard, Dong Zhao, Kathryn Metzger, Joshua T. White, Michael R. Sivack, Kenneth J. Mcclellan, Edward J. Lahoda & Jie Lian. (2022) UN and U3Si2 composites densified by spark plasma sintering for accident-tolerant fuels. Ceramics International 48:8, pages 10762-10769.
Crossref
Crossref
Daxi Guo, Hengfeng Gong, Lei Li, Jian Wen, Yiran Xie, Qisen Ren, Yehong Liao & Tong Liu. (2022) Ionization-induced defect annealing by fission product ions in SiC and its implication for UO2-SiC composite fuels. Journal of Nuclear Materials 560, pages 153474.
Crossref
Crossref
David H. Hurley, Anter El-Azab, Matthew S. Bryan, Michael W. D. Cooper, Cody A. Dennett, Krzysztof Gofryk, Lingfeng He, Marat Khafizov, Gerard H. Lander, Michael E. Manley, J. Matthew Mann, Chris A. Marianetti, Karl Rickert, Farida A. Selim, Michael R. Tonks & Janelle P. Wharry. (2021) Thermal Energy Transport in Oxide Nuclear Fuel. Chemical Reviews 122:3, pages 3711-3762.
Crossref
Crossref
Jennifer K. Watkins, Adrian R. Wagner, Scott C. Middlemas, M. Craig Marshall, Kathryn Metzger & Brian J. Jaques. (2022) Enhancing thermal conductivity of UO2 with the addition of UB2 via conventional sintering techniques. Journal of Nuclear Materials 559, pages 153421.
Crossref
Crossref
Denise das M. Camarano, Fábio A. Mansur & Ana Maria Matildes dos Santos. (2021) Thermal conductivity of gadolinia-chromia doped UO fuel. Measurement: Sensors 18, pages 100157.
Crossref
Crossref
Yi Zhong, Zhenliang Yang, Qiqi Huang, Zhiyi Wang, Yun Wang, Dezhi Zhang, Tao Shi, Min Wu, Bingqing Li, Rui Gao, Mingfu Chu, Pengcheng Zhang & Bin Bai. (2021) Sintering behavior and thermal conductivity of graphite flakes/uranium dioxide composites. Journal of Nuclear Materials 555, pages 153106.
Crossref
Crossref
Dezhi Zhang, Yingru Li, Zhenliang Yang, Bingqing Li, Zhiyi Wang, Qiqi Huang, Biaojie Yan, Mingfu Chu, Libing Yu, Rongguang Zeng, Pengcheng Zhang, Bin Bai, Rui Gao & Xinchun Lai. (2021) In-situ synthesized nanocrystalline UO2/SiC composite with superior thermal conductivity. Ceramics International 47:22, pages 31160-31167.
Crossref
Crossref
Heung Soo Lee, Dong Seok Kim, Dong-Joo Kim, Jae Ho Yang, Ji-Hae Yoon, Yang-Hyun Koo & Kun Woo Song. (2021) Numerical investigation of the thermal conductivity of UO2 – Mo microplate fuel pellets to realize enhanced heat transfer in the fuel radial direction. Journal of Nuclear Materials 554, pages 153075.
Crossref
Crossref
Dong-Hoon Yang, Young-Kyun Kim, Sun-Hong Park & Kee-Ahn Lee. (2021) Improved mechanical and thermophysical properties of additively manufactured Cu-Ni-Sn-P alloy by using aging treatment. Journal of Alloys and Compounds 875, pages 160050.
Crossref
Crossref
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.
Crossref
Crossref
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.
Crossref
Crossref
Ping Chen, Bowen Qiu, Yuanming Li, Yingwei Wu, Yongbo Hui, Yangbin Deng & Kun Zhang. (2021) An evaluation on in-pile behaviors of SiCf/SiC cladding under normal and accident conditions with updated FROBA-ATF code. Nuclear Engineering and Technology 53:4, pages 1236-1249.
Crossref
Crossref
Floyd W. Hilty, Dong-Uk Kim & Michael R. Tonks. (2021)
Impact of fission gas bubbles on thermal conductivity of UO
fuels with high thermal conductivity additives
. Journal of Nuclear Materials 546, pages 152779.
Crossref
Crossref
Bingqing Li, Zhenliang Yang, Zhiyi Wang, Qiqi Huang, Xuxu Liu, Biaojie Yan, Liang Cheng, Tao Shi, Dezhi Zhang, Min Wu, Rui Gao, Mingfu Chu, Pengcheng Zhang & Bin Bai. (2021) Graphite flakes/UO2 fuel pellets with excellent thermal conductivity in radial direction. Journal of Nuclear Materials 545, pages 152639.
Crossref
Crossref
E. Kardoulaki, D.M. Frazer, J.T. White, U. Carvajal, A.T. Nelson, D.D. Byler, T.A. Saleh, B. Gong, T. Yao, J. Lian & K.J. McClellan. (2021) Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering. Journal of Nuclear Materials 544, pages 152690.
Crossref
Crossref
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.
Crossref
Crossref
Floyd W. Hilty & Michael R. Tonks. (2020) Development and application of a microstructure dependent thermal resistor model for UO2 reactor fuel with high thermal conductivity additives. Journal of Nuclear Materials 540, pages 152334.
Crossref
Crossref
Biaojie Yan, Rui Gao, Pengchuang Liu, Pengcheng Zhang & Liang Cheng. (2020) Optimization of thermal conductivity of UO2–Mo composite with continuous Mo channel based on finite element method and machine learning. International Journal of Heat and Mass Transfer 159, pages 120067.
Crossref
Crossref
T.P. Kaloni, N. Onder, J. Pencer & E. Torres. (2020)
approach on the electronic and thermal properties of hypostoichiometric
. Annals of Nuclear Energy 144, pages 107511.
Crossref
Crossref
Honghao Yu, Zhijie Chen & Jiejin Cai. (2020) Accident tolerant fuel thermal hydraulic behaviors evaluation during loss of coolant accident in CPR1000. Annals of Nuclear Energy 139, pages 107273.
Crossref
Crossref
Shengli Chen & Cenxi Yuan. (2020) Neutronic study of UO2-BeO fuel with various claddings. Nuclear Materials and Energy 22, pages 100728.
Crossref
Crossref
Nicholas R. Brown, Andrew T. Nelson & Kurt A. Terrani. 2020. Comprehensive Nuclear Materials. Comprehensive Nuclear Materials
684
706
.
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.
Crossref
Crossref
D. M. Camarano, F. A. Mansur, A. M. M. Santos, L. S. Ribeiro & A. Santos. (2019) Thermal Conductivity of UO2–BeO–Gd2O3 Nuclear Fuel Pellets. International Journal of Thermophysics 40:12.
Crossref
Crossref
Yanan He, Koroush Shirvan, Yingwei Wu & G.H. Su. (2019) Fuel performance optimization of U3Si2-SiC design during normal, power ramp and RIA conditions. Nuclear Engineering and Design 353, pages 110276.
Crossref
Crossref
J. Buckley, J.D. Turner & T.J. Abram. (2019) Uranium dioxide - Molybdenum composite fuel pellets with enhanced thermal conductivity manufactured via spark plasma sintering. Journal of Nuclear Materials 523, pages 360-368.
Crossref
Crossref
Jie Wei, Wei Zhou, Song Li, Pei Shen, Shuai Ren, Alice Hu & Wenzhong Zhou. (2019) Modified Embedded Atom Method Potential for Modeling the Thermodynamic Properties of High Thermal Conductivity Beryllium Oxide. ACS Omega 4:4, pages 6339-6346.
Crossref
Crossref
Sang-Chae Jeon, Jae-Won Lee, Joo-Young Yoon, Yung-Zun Cho, Dong-Joo Kim, Dong Seok Kim, Keon Sik Kim, Jong Hun Kim & Jae Ho Yang. (2019) Stimulation of densification during the reduction of U3O8 to UO2 by atmosphere control. Ceramics International 45:6, pages 6863-6868.
Crossref
Crossref
Bingqing Li, Zhenliang Yang, Mingfu Chu, Qiqi Huang, Zhiyi Wang, Rui Gao, Yi Zhong, Xuxu Liu, Limei Duan & Pengcheng Zhang. (2018) Ti3SiC2/UO2 composite pellets with superior high-temperature thermal conductivity. Ceramics International 44:16, pages 19846-19850.
Crossref
Crossref
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.
Crossref
Crossref
Yangbin Deng, Koroush Shirvan, Yingwei Wu & Guanghui Su. (2018) Probabilistic view of SiC/SiC composite cladding failure based on full core thermo-mechanical response. Journal of Nuclear Materials 507, pages 24-37.
Crossref
Crossref
Bingqing Li, Zhenliang Yang, Jianping Jia, Pengcheng Zhang, Rui Gao, Tong Liu, Rui Li, Huawei Huang, Maozhou Sun & Dandan Mazhao. (2018) High temperature thermal physical performance of SiC/UO 2 composites up to 1600 °C. Ceramics International 44:9, pages 10069-10077.
Crossref
Crossref
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.
Crossref
Crossref
Bingqing Li, Zhenliang Yang, Jianping Jia, Yi Zhong, Xuxu Liu, Pengcheng Zhang, Rui Gao, Tong Liu, Rui Li, Huawei Huang, Maozhou Sun & Dandan Mazhao. (2018) High temperature thermal physical performance of BeO/UO2 composites prepared by spark plasma sintering (SPS). Scripta Materialia 142, pages 70-73.
Crossref
Crossref
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.
Crossref
Crossref
Qusai M. Mistarihi, Vivek Raj, Joon Hui Kim & Ho Jin Ryu. (2017) Thermal conductivity of Mo-reinforced ZrO2 composites fabricated by spark plasma sintering for inert matrix fuels. Materials & Design 134, pages 476-485.
Crossref
Crossref
D. M. Camarano, F. A. Mansur, A. M. M. Santos, W. B. Ferraz & R. A. N. Ferreira. (2017) Effects of Beryllium and Compaction Pressure on the Thermal Diffusivity of Uranium Dioxide Fuel Pellets. International Journal of Thermophysics 38:9.
Crossref
Crossref
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.
Crossref
Crossref
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.
Crossref
Crossref
W. Peiman, I.L. Pioro, K. Gabriel & M. Hosseiny. 2016. Handbook of Generation IV Nuclear Reactors. Handbook of Generation IV Nuclear Reactors
583
635
.
Zhichao Chen, Ghatu Subhash & James S. Tulenko. (2015) Spark plasma sintering of diamond-reinforced uranium dioxide composite fuel pellets. Nuclear Engineering and Design 294, pages 52-59.
Crossref
Crossref
Wenzhong Zhou, Rong Liu & Shripad T. Revankar. (2015) Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2–BeO fuel in light water reactors. Annals of Nuclear Energy 81, pages 240-248.
Crossref
Crossref
W. PeimanI. PioroK. Gabriel. (2015) Thermal-Hydraulic and Neutronic Analysis of a Reentrant Fuel-Channel Design for Pressure-Channel Supercritical Water-Cooled Reactors. Journal of Nuclear Engineering and Radiation Science 1:2.
Crossref
Crossref
A. A. Kovalishin, V. N. Prosyolkov, V. D. Sidorenko & Yu. V. Stogov. (2014) On the possibility of using uranium-beryllium oxide fuel in a VVER reactor. Physics of Atomic Nuclei 77:14, pages 1661-1663.
Crossref
Crossref
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.
Crossref
Crossref
K.H. Sarma, J. Fourcade, S-G. Lee & A.A. Solomon. (2006) New processing methods to produce silicon carbide and beryllium oxide inert matrix and enhanced thermal conductivity oxide fuels. Journal of Nuclear Materials 352:1-3, pages 324-333.
Crossref
Crossref