Heat Transfer Modeling and Computational Experiment for Uranium Dioxide Fuel Fragment Surrounded by Concrete

cba21b1a-855d-4b50-be2f-befab517a1eb20220321081601084wseas:wseasmdt@crossref.orgMDT DepositMOLECULAR SCIENCES AND APPLICATIONS10.37394/232023https://wseas.com/journals/msa/index.php112021112021110.37394/232023.2021.1https://wseas.com/journals/msa/2021.phpHeat Transfer Modeling and Computational Experiment for Uranium Dioxide Fuel Fragment Surrounded by ConcreteJamshidGharakhanlouDept of Heat and Power, National Technical University of Ukraine “KPI”, UKRAINEIvan V.KazachkovDept of Energy Technology, Royal Institute of Technology, Stockholm, 10044, 6:('(1Serge V.ChernyshenkoInformation Systems Institute, University Koblenz-Landau, GERMANYThe problem is of interest for nuclear power safety and some other fields. Non-stationary twodimensional boundary task for non-linear heat flow process in cylindrical rod of dioxide uranium surrounded by cylindrical concrete layer is considered with account of the real physical properties of materials depending on temperature, as well as accounting an internal heat generation of radioactive material. The mathematical model of a heat transfer process is realized as computer program for the FLEX PDE platform. Based on the model the computational experiments have been performed and their analysis was made. The results obtained maybe useful by performing the nuclear safety analysis, as well as by model calculations in constructing the passive protection systems against severe accidents at the nuclear power plants.8162021816202142528https://wseas.com/journals/msa/2021/a16msa-008(2021).pdf10.37394/232023.2021.1.8https://wseas.com/journals/msa/2021/a16msa-008(2021).pdfKazachkov I.V. Konovalikhin M.J., Sehgal B.R. Coolability of melt pools and debris beds with bottom injection/ 2nd Jap.-Europ. Two-Phase Flow Group Meeting (Tsukuba, Japan, 2000).- P. 90-96. Haraldsson H.O., Kazachkov I.V., Dinh T.N., Sehgal B.R. Analysis of thin jet breakup length in immiscible fluids/ Abstr. 3rd Int. Conf. Adv. in Fluid Mechanics (Montreal, Canada, 24-26 May, 2000).- P. 43-47. Park H.S., Kazachkov I.V., Sehgal B.R. et al. Analysis of Plunging Jet Penetration into Liquid Pool in Isothermal Conditions/ ICMF 2001: 4th Int. Conf. Multiphase Flow (New Orleans, Louisiana, USA, May 27-June 1, 2001).- P.65- 69. Kazachkov I.V., Paladino D., Sehgal B.R. Exvessel coolability of a molten pool by coolant injection from submerged nozzles/ 9 th Int. Conf. Nucl. Energy Devel (April 8-12, 2001. Nice, France). - P. 43 - 49. 10.1615/jenhheattransf.v8.i6.40Kazachkov I.V., Konovalikhin M.J., Sehgal B.R. Dryout Location in a Low-porosity Volumetrically Heated Particle Bed// J. of Enhanced Heat Transfer.- 2001.- V.8, No. 6. - P. 397 - 410. 10.1016/s1290-0729(02)01394-7Kazachkov I.V., Konovalikhin M.J. A Model of a Steam Flow through the Volumetrically Heated Particle Bed// Int. J. of Thermal Sciences. - 2002. - Vol. 41. - P. 1077 - 1087. Kazachkov I.V., Mogaddam Ali Hassan. Modeling of thermal hydraulic processes during severe accidents at NPP.- К.: NTUU «KPI», 2008.- 172 с. (In Russian). Kalvand Аli, Kazachkov I.V. Modeling of Corium Melt Cooling During Severe Accidents at Nuclear Power Plants/ Recent Advances in Continuum Mechanics (special issue)/ Proc. IASME/WSEAS Int. Conf.- Univ. of Cambridge, 2009. - P. 200 - 207. Vakhid Hasani Mogaddam, I.V. Kazachkov. Modeling of corium jet penetration into the pool of volatile coolant under reactor vessel// Nuclear physics and energy.- 2010.- №2.- P. 151-158. Vahid Hasani Moghaddam, І.V. Каzachkov. About modeling of the corium jet penetrating the pool of volatile coolant under reactor vessel/ Іnt. Conf. on Applied Computer Science (ACS). - Malta, 15-17 September 2010. - р. 89-95. Kazachkov I.V., Konoval O.V. Non-linear mathematical models for the jets penetrating liquid pool of different density under diverse physical conditions and their simulation// WSEAS transactions on applied and theoretical mechanics. – № 2, Vol. 8, 2013.– P. 156-169. Konoval O.V., Kalvand Аli, Kazachkov I.V. Modeling of corium cooling and analysis of the factors of containment loading during severe accidents // Nuclear physics and energy.- 2013.- P. 276-287. (In Russian). Rovno NPP. Power Unit № 1. Technical substatiation of the safety of construction and operation of NPP. Attachment 2.- 1998. Chirkin V.S. Thermal physics properties of materials for nuclear installations. М.: Atomizdat.- 1967.- 474 pp. (In Russian). Kirillov P.L., Bogoslovskaya G.P. Heat transfer in nuclear power installations: Textbook for universities.- М.: Energoatomizdat.- 2000.- 456 pp. (In Russian). Project for advanced safety analysis of Unit №1 Khmelnitsky AES. Data base by nuclear vapor generating device. BOA 301913-A-R4. 2001. Krasnoshchekov Е.А., Sukomel А.S. Exercises by heat transfer: Textbook. Ed. 4th, redone.- М.: Energiya.- 1980.- 288 pp. (In Russian).