Neutronic analysis of a fuel element with variations in fuel enrichment and burnable poison by R de Faria, Felipe Martins, Carlos Velasquez, Angela Fortini, Claubia Pereira

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A method for VVER fuel element cladding reliability prediction by S. M. Pelykh, M. V. Maksimov, M. V. Nikolsky

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Polymeric membranes grafted by ionizing radiation for uranium adsorption by Amanda Caroline Patricio Cardoso, Rafael Henrique Lazzari Garcia, Elita Fontenele Urano de Carvalho, Mohamad Al-Sheikhly, Yasko Kodama

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Performance investigation of UN spherical fuel elements in MSR-SF by Haiqing Zhang, Changqing Cao, Peng Wang, Ziwei Li, Xuzhong Kang, Jun Lin

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Critical Velocity Experimental Assessment in Flat Plate Fuel Element for Nuclear Research Reactor by Delvonei Alves Andrade, Javier Gonzalez Mantecón, Roberto Navarro de Mesquita, Miguel Mattar Neto, Pedro Ernesto Umbehaun, Walmir Maximo Torres

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Thermal-hydraulic calculations of the WWR-SM research reactor by S. A. Baytelesov, F. R. Kungurov, B. S. Yuldashev

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An analysis of the fuel element cladding failure parameter considering the nonuniformity of energy release in a fuel assembly by S. N. Pelykh, M. V. Maksimov, S. D. Ryabchikov

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Estimation of local linear heat rate jump values in the variable loading mode by S. N. Pelykh, R. L. Gontar, T. V. Tsiselskaya

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Method of Quality Control of Nuclear Reactor Element Tightness to Improve Environmental Safety by Eduard Khomiak, Roman Trishch, Joanicjusz Nazarko, Miloslav Novotný, Vladislavas Petraškevičius

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Simulation research on the blister evolution behaviors of UMo/Zr monolithic fuel elements by Tang Changbing, Yan Feng, Jiao Yongjun, Xin Yong, Pu Zengping, Xiao Zhong

Subjects: “…UMo/Zr monolithic fuel element…”
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SIMULATION OF ELECTRONIC EQUIPMENT ELEMENTS COOLING IN SOLIDWORKS by Arkady N. SOLOVIEV, Leila V. GLAZUNOVA

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Using a user–defined function in Ansys Fluent to implement the energy release profile in model fuel elements taking into account radiation heating by Н.А. Сулейменов, Н.Е. Мухамедов, О.М. Жанболатов

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