Open Access
Issue |
E3S Web Conf.
Volume 592, 2024
International Scientific Conference Energy Management of Municipal Facilities and Environmental Technologies (EMMFT-2024)
|
|
---|---|---|
Article Number | 03009 | |
Number of page(s) | 6 | |
Section | Energy Production, Storage, and Distribution | |
DOI | https://doi.org/10.1051/e3sconf/202459203009 | |
Published online | 20 November 2024 |
- Kanareikin A. 2023 Investigation of the thermally stressed state of an elliptical shell. E3S Web of Conferences 460 07024 [CrossRef] [EDP Sciences] [Google Scholar]
- Kanareikin A. I. 2021 Mathematical modeling of the thermally stressed state of elliptical-section concrete structures, Journal of Physics: Conference Series 012013 [Google Scholar]
- Kanareikin A. 2023 Mathematical modeling of temperature stresses of heat-generating elements of elliptical cross-section. E3S Web of Conferences 376 01064 [CrossRef] [EDP Sciences] [Google Scholar]
- Kanareikin A. 2023 Determination of the optimal size of the fuel element of the elliptical cross-section of a nuclear reactor. E3S Web of Conferences 376 01066 [CrossRef] [EDP Sciences] [Google Scholar]
- Kanareikin A. 2023 Friction and wear of elements of nuclear reactors. E3S Web of Conferences 402 05024 [CrossRef] [EDP Sciences] [Google Scholar]
- Kanareikin A. 2023 Simplified dynamic model of a nuclear reactor. E3S Web of Conferences 402 05025 [CrossRef] [EDP Sciences] [Google Scholar]
- Geelhood K. J., Luscher W. G., Beyer C.E., Cuta J. M. 2011 FRAPTRAN: a computer code for the transient analysis of oxide fuel rods. Washington (DC): United States Nuclear Regulatory Commission [Google Scholar]
- Thouvenin G., Ricaud J. M., Michel B., Plancq D., Thevenin P. 2006 ALCYONE: the PLEIADES fuel performance code dedicated to multidimensional PWR studies. Top Fuel 2006 International Meeting [Google Scholar]
- Anders Logg, Kent-Andre Mardal, Garth N. 2011 Wells Automated Solution of Differential Equations by the Finite Element Method. The FEniCS Book [Google Scholar]
- Amosova E. V., Shishkin A. V. 2017 Calculation of Distribution Dynamics of Inhomogeneous Temperature Field in Range of Fuel Elements by Using FreeFem++/. IOP Conference Series: Materials Science and Engi-neering 262 7 [Google Scholar]
- Wilcox D. C. 2006 Turbulence modeling for CFD. DCW industries 522 [Google Scholar]
- Shvetsov Yu. E., Kouznetsov I. A. 2011 Analytical Studies on Thermal-Hydraulic Parameters of Fast Reactor Taking into Account Effect of Interwrapper Space. Journal of Materials Science and Engineering B 1 (7) 938–946 [Google Scholar]
- Yamano H., Fujita S., Tobita Y., Sato I., Niwa H. 2008 Development of a threedimensional CDA analysis code: SIMMER-IV and its first application to reactor case. Nuclear Engineering and Design 238 66–73 [CrossRef] [Google Scholar]
- Ramirez J. C., Stan M., Cristea P. 2006 Simulations of heat and oxygendiffusion in UO2 nuclear fuel rods. Journal of nuclear materials 359(3) 174–184 [CrossRef] [Google Scholar]
- Mihaila B. 2009 Simulations of coupled heat transport, oxygen diffusion, and thermal expansion in UO2 nuclear fuel elements. Journal of Nuclear Materials 394(2) 182–189 [CrossRef] [Google Scholar]
- Hales J. D. 2015 Asymptotic expansion homogenization for multiscale nuclear fuel analysis. Computational Materials Science 99 290–297 [CrossRef] [Google Scholar]
- Rashid Y., Dunham R., Montgomery R. 2004 Fuel analysis and licensing code: FALCON MOD0. EPRI Report 1011308 [Google Scholar]
- Philip B. 2015 A parallel multi-domain solution methodology applied to nonlinear thermal transport problems in nuclear fuel pins. Journal of Computational Physics 286 143–171 [Google Scholar]
- Geelhood K. J., Luscher W. G., Beyer C.E., Cuta J. M. 2011 FRAPTRAN: a computer code for the transient analysis of oxide fuel rods. Washington (DC): United States Nuclear Regulatory Commission [Google Scholar]
- Thouvenin G., Ricaud J. M., Michel B., Plancq D., Thevenin P. 2006 ALCYONE: the PLEIADES fuel performance code dedicated to multidimensional PWR studies. Top Fuel 2006 International Meeting [Google Scholar]
- Semenovich, O.V., Modeling of Thermohydrodynamic Processes in Fuel Rod Assemblies of Water Cooled Reactors. MTA Energiatudományi Kutatóközpont, Budapest Part 2. P. 649–665. [Google Scholar]
- Kanareikin A. 2023 Heat exchange between the heat-generating element of the circular section of a nuclear reactor and its shell under boundary conditions of the fourth kind. E3S Web of Conferences 371 05014 [CrossRef] [EDP Sciences] [Google Scholar]
- Kanareikin A. 2023 Heat exchange between the fuel element of a nuclear reactor made of plutonium dioxide and its shell under boundary conditions of the fourth kind. E3 S Web of Conferences 371 03025 [CrossRef] [EDP Sciences] [Google Scholar]
- Kanareikin A. 2023 Determination of the optimal size of the fuel element of the elliptical cross-section of a nuclear reactor. E3S Web of Conferences 376 01066 [CrossRef] [EDP Sciences] [Google Scholar]
- Kanareikin A. 2023 Mathematical modeling of temperature stresses of heat-generating elements of elliptical cross-section. E3S Web of Conferences 376 01064 [CrossRef] [EDP Sciences] [Google Scholar]
- Kanareikin A. 2023 Heat exchange between the fuel element of a nuclear reactor made of uranium oxide and its shell under boundary conditions of the fourth kind. E3S Web of Conferences 411 01056 [CrossRef] [EDP Sciences] [Google Scholar]
- Kanareikin A. I. 2023 Ways to reduce friction and wear of fuel elements in nuclear power. BIO Web of Conferences 71 02018 [CrossRef] [EDP Sciences] [Google Scholar]
- Kanareikin A. I. 2022 Determination of the optimal size of the heat-generating element of the elliptical cross-section of a nuclear reactor in order to reduce the arising temperature stresses. AIP Conference Proceedings 2762 020007 [CrossRef] [Google Scholar]
- Kanareikin A. I. 2022 Mathematical modeling of the fuel element of a nuclear reactor taking into account the temperature dependence of the thermal conductivity of the fuel element made of uranium oxide. IOP Conference Series: Earth and Environmental Science 990 012012 [CrossRef] [Google Scholar]
- Kanareikin A. I. 2022 Simulation of a fuel element made of plutonium dioxide. IOP Conference Series: Earth and Environmental Science 1045 012070 [CrossRef] [Google Scholar]
Current usage metrics show cumulative count of Article Views (full-text article views including HTML views, PDF and ePub downloads, according to the available data) and Abstracts Views on Vision4Press platform.
Data correspond to usage on the plateform after 2015. The current usage metrics is available 48-96 hours after online publication and is updated daily on week days.
Initial download of the metrics may take a while.