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

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F11%3A%230001100" target="_blank" >RIV/46356088:_____/11:#0001100 - isvavai.cz</a>

Výsledek na webu

—

DOI - Digital Object Identifier

—

Jazyk výsledku

angličtina

Název v původním jazyce

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

Popis výsledku v původním jazyce

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 submode

Název v anglickém jazyce

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

Popis výsledku anglicky

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 submode

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

CEP obor

JF - Jaderná energetika

OECD FORD obor

—

Projekt

<a href="/cs/project/ME10142" target="_blank" >ME10142: Experimentální výzkum procesů porušení ozářeného povlaku palivových proutků jaderného paliva ? ?OECD Studsvik Cladding Integrity Project II?.</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2011

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název periodika

Journal of Materials Science and Engineering B

ISSN

2161-6221

e-ISSN

—

Svazek periodika

1

Číslo periodika v rámci svazku

3

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

9

Strana od-do

323-331

Kód UT WoS článku

—

EID výsledku v databázi Scopus

—