Finite element and boundary element solution of nuclear waste repository thermal dimensioning problem
dc.contributor.author | Hokr, Milan | |
dc.contributor.author | Novák, Josef | |
dc.date.accessioned | 2017-11-02 | |
dc.date.available | 2017-11-02 | |
dc.date.issued | 2012 | |
dc.description.abstract | We solve the thermal dimensioning problem of the deep geological spent nuclear fuel repository, which means to estimate the maximum temperature in the repository caused by the heat generation of the spent fuel. We use a combination of the boundary element method for the exterior problem of heat discharge to the infinity and finite element method for a near- field thermal problem with a boundary condition expressed by the far-field problem solution. This combination is implemented within the simulation software ANSYS as the “far-field element”. The far-field element solution confirmed to well represent the heat discharge, in comparison with the variant of a standard FEM far-field problem solution and conventional boundary conditions (constant temperature or zero heat flow). | en |
dc.format | text | cs |
dc.format.extent | 7 stran | |
dc.identifier.eissn | 1803-9790 | |
dc.identifier.issn | 1803-9782 | |
dc.identifier.other | ACC_2012_4_11 | |
dc.identifier.uri | https://dspace.tul.cz/handle/15240/21143 | |
dc.language.iso | en | |
dc.license | CC BY-NC 4.0 | |
dc.publisher | Technická univerzita v Liberci, Česká republika | cs |
dc.relation.isbasedon | ANSYS, Inc.: Release 12.0 Documentation for ANSYS, ANSYS Incorporated, 2009. | |
dc.relation.isbasedon | HÖKMARK H., FÄLTH B.: Thermal dimensioning of the deep repository. Influence of canister spacing, canister power, rock thermal properties and nearfield design on the maximum canister surface temperature, SKB report nr. TR-03-09, 2003. | |
dc.relation.isbasedon | IAEA: Scientific and Technical Basis for the Geological Disposal of Radioactive Wastes, Int.Atom. En. Ag., Technical Reports Series No. 413, 2003. | |
dc.relation.isbasedon | IKONEN, K.: Thermal Analyses of Spent Nuclear Fuel Repository, technical report, POSIVA 2003-04. | |
dc.relation.isbasedon | KALJEVIC, I., SAIGAL, S., ALI, A.: An Infinite Boundary Element Formulation for Three-Dimensional Potential Problems, International Journal for Numerical Methods in Engineering, Vol. 35, No. 10, pp. 2079-2100 (1992) . | |
dc.relation.isbasedon | KOHUT R, BLAHETA R, KOLCUN A, MALÍK J AND STARÝ J, Computations of thermo-elastic responses of rocks in the vicinity of geological deposition of the spent nuclear fuel, In: Proceedings of SIMONA 2006, Technical University of Liberec, 2006, pp. 70-77. | |
dc.relation.isbasedon | SÚRAO: Zadávací bezpečnostní zpráva, Příloha č. 1, Referenční projekt hlubin-ného úložiště v hostitelském prostředí granitových hornin, SURAO-EGP Invest, Uh. Brod 1999. | |
dc.relation.isbasedon | ÚJV ŘEŽ a.s.: Shromáždění a aktualizace vstupních údajů o vývoji tepla vyhořelých palivových souborů, Výstup 1.2, Ev. č. zhotovitele: 5 SMP 156, Nuclear research institute Řež, March 2006. | |
dc.relation.ispartof | ACC Journal | en |
dc.relation.isrefereed | true | |
dc.subject | heat conduction | en |
dc.subject | numerical simulation | en |
dc.subject | far-field element | en |
dc.subject | multiscale | en |
dc.subject | ANSYS | en |
dc.title | Finite element and boundary element solution of nuclear waste repository thermal dimensioning problem | en |
dc.type | Article | en |
local.access | open | |
local.citation.epage | 101 | |
local.citation.spage | 95 | |
local.fulltext | yes | en |
local.relation.issue | 4 | |
local.relation.volume | 18 |
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