Simulation of the compression test of the Zr1Nb fuel cladding ring by Vojtěch Smolík, Alžběta Endrychová, Jakub Krejčí

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STUDY OF THERMAL CREEP OF COATED CLADDING MATERIALS by Martin Ševeček, Koroush Shirvan, Ronald G. Ballinger

Subjects: “…Accident Tolerant Fuel, Fuel Cladding, Creep, Coating…”
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COATED CLADDING BEHAVIOR DURING HIGH-TEMPERATURE TRANSIENTS by Adéla Chalupová, Jakub Krejčí, Ladislav Cvrček, Martin Ševeček, Vojtěch Rozkošný, Antonín Přibyl, Patricie Halodová, Petra Gávelová

Subjects: “…nuclear fuel, fuel cladding, loca, atf, coating, pvd.…”
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Experimental Study on Interaction between Ce-Nd Alloy and Stainless Steel by RUAN Zhangshun, ZHANG Ruiying, WANG Yuhui, TU Menghe, FU Xiaogang, LONG Bin

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NEUTRONIC ANALYSIS OF THE CANDIDATE MULTI-LAYER CLADDING MATERIALS WITH ENHANCED ACCIDENT TOLERANCE FOR WWER REACTORS by Ondřej Novák, Martin Ševeček

Subjects: “…WWER, Nuclear Fuel, Cladding, Accident Tolerant Fuel, Neutronics, Serpent…”
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Molecular Dynamics Simulation of Thermal and Irradiation Creep Behavior of FeCrAl Alloy for Nuclear Fuel Cladding by Bei CAO, Wenxiu BAI, Huan YAO, Junmei WU, Chunyu YIN, Ping CHEN

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HIGH-TEMPERATURE OXIDATION OF CHROME-NICKEL ALLOY by Adéla Chalupová, Martin Steinbrück, Mirco Grosse, Jakub Krejčí, Martin Ševeček

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Visual Experimental Study of Influence of Fuel Rod Bundle Spacing on Fission Gas Release under Fuel Cladding Failure Conditions by LI Shengkang, CAI Jiejin

Subjects: “…fuel cladding failure…”

Research Progress on Ferritic/Martensitic Steels for Integrated Fast Reactor Fuel Cladding by Feng　Wei, Guan　Songyuan, Li　Junhong, Shan　Pengzhan, Xing　Weiwei, Hao　Xianchao, Liang　Tian, Ma　Yingche

Subjects: “…integrated fast reactor； fuel cladding； ferritic/martensitic steel； irradiation performance； creep property…”
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Accurate segmentation of localized fuel cladding chemical interaction layers in SEM micrographs with deep learning method by Liang Zhao, Yachun Wang, Fei Xu

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Improved damage tolerance of SiC-based nuclear fuel cladding with novel multi-layered SiC coating design at 1200 °C by Guanjie Yuan, David H. Cook, Harold Barnard, Edward Lahoda, Peng Xu, Robert O. Ritchie, Dong Liu

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Experimental Study on CHF Limit of Cr-coated Fuel Cladding under High Temperature and High Pressure Flow Condition by FAN Guanhua, FANG Qifei, YAO Xi, PENG Zhenxun, GUO Ming, CHEN Senyang, LYU Lulu, ZHANG Ge, SU Qianhua, LU Donghua

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IMITATING NEUTRON IRRADIATION DAMAGE USING A COMBINATION OF ION BEAMS by Václav Šísl, Martin Ševeček

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NANOINDENTATION OF HYDROGEN ENRICHED Zr-1Nb ZIRCONIUM ALLOY NUCLEAR FUEL CLADDINGS by Ondřej Libera, Patricie Halodová, Petra Gávelová, Jakub Krejčí

Subjects: “…nanoindentation, nuclear fuel claddings, zr-1nb…”
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