About: Complex FEM based system of computer codes to model nuclear fuel rod thermo-mechanical behaviour

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About: Complex FEM based system of computer codes to model nuclear fuel rod thermo-mechanical behaviour Goto Sponge NotDistinct Permalink

An Entity of Type : http://linked.opendata.cz/ontology/domain/vavai/Vysledek, within Data Space : linked.opendata.cz associated with source document(s)

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rdf:type	skos:Concept http://linked.opendata.cz/ontology/domain/vavai/Vysledek
Description	Modeling of the thermo-mechanical behavior of the nuclear fuel rod allows to assess the temperatures and stresses that can be used to determine if the fuel rod will operate without failures during proposed steady state conditions and permitted power ramps and also during unexpected power excursions. The paper presents long-term effort to establish closed chain of computer codes, which allow computer modeling of the thermo-mechanical fuel rod behavior from the one dimensional (1D) representation to the 3D detailed problem description. The whole complex uses the same finite element method (FEM) based mathematical approach. The principle of this modular approach is to handle boundary and initial conditions by the similar transfer independent on the complexity of solved problem. We have combined the integral code to the full 2D (r-z) global model of fuel pin ending at 2D (r-z, r-F) and 3D local detailed submodels. The system of codes is connected (coupled) by data transfer. All the submodels are stand-alone. The same is valid for the material data properties. Examples of simulations results of all the described modeling levels are documented by figures. Modeling of the thermo-mechanical behavior of the nuclear fuel rod allows to assess the temperatures and stresses that can be used to determine if the fuel rod will operate without failures during proposed steady state conditions and permitted power ramps and also during unexpected power excursions. The paper presents long-term effort to establish closed chain of computer codes, which allow computer modeling of the thermo-mechanical fuel rod behavior from the one dimensional (1D) representation to the 3D detailed problem description. The whole complex uses the same finite element method (FEM) based mathematical approach. The principle of this modular approach is to handle boundary and initial conditions by the similar transfer independent on the complexity of solved problem. We have combined the integral code to the full 2D (r-z) global model of fuel pin ending at 2D (r-z, r-F) and 3D local detailed submodels. The system of codes is connected (coupled) by data transfer. All the submodels are stand-alone. The same is valid for the material data properties. Examples of simulations results of all the described modeling levels are documented by figures. (en)
Title	Complex FEM based system of computer codes to model nuclear fuel rod thermo-mechanical behaviour Complex FEM based system of computer codes to model nuclear fuel rod thermo-mechanical behaviour (en)
skos:prefLabel	Complex FEM based system of computer codes to model nuclear fuel rod thermo-mechanical behaviour Complex FEM based system of computer codes to model nuclear fuel rod thermo-mechanical behaviour (en)
skos:notation	RIV/46356088:_____/11:#0001100!RIV12-MSM-46356088
http://linked.open...avai/predkladatel	ÚJV Řež, a. s.
http://linked.open...avai/riv/aktivita	P
http://linked.open...avai/riv/aktivity	P(ME10142)
http://linked.open...iv/cisloPeriodika	3B
http://linked.open...vai/riv/dodaniDat	2012
http://linked.open...aciTvurceVysledku	Valach, Mojmír Zymák, Jiří Dostál, Martin
http://linked.open.../riv/druhVysledku	J - Článek v odborném periodiku
http://linked.open...iv/duvernostUdaju	S - Úplné a pravdivé údaje nepodléhající ochraně podle zvláštních právních předpisů
http://linked.open...titaPredkladatele	ÚJV Řež, a. s.
http://linked.open...dnocenehoVysledku	191393
http://linked.open...ai/riv/idVysledku	RIV/46356088:_____/11:#0001100
http://linked.open...riv/jazykVysledku	eng - angličtina
http://linked.open.../riv/klicovaSlova	thermo-mechanical behaviour; nuclear fuel; finite element method; modelling (en)
http://linked.open.../riv/klicoveSlovo	finite element method modelling nuclear fuel thermo-mechanical behaviour
http://linked.open...odStatuVydavatele	US - Spojené státy americké
http://linked.open...ontrolniKodProRIV	[969782EB9523]
http://linked.open...i/riv/nazevZdroje	Journal of Materials Science and Engineering B
http://linked.open...in/vavai/riv/obor	JF
http://linked.open...ichTvurcuVysledku	3 (xsd:int)
http://linked.open...cetTvurcuVysledku	3 (xsd:int)
http://linked.open...vavai/riv/projekt	Irradiated nuclear fuel rod cladding failure process experimental research – „OECD Studsvik Cladding Integrity Project II“.
http://linked.open...UplatneniVysledku	2011
http://linked.open...v/svazekPeriodika	1
http://linked.open...iv/tvurceVysledku	Dostál, Martin Valach, Mojmír Zymák, Jiří
issn	2161-6221
number of pages	9 (xsd:int)

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