Calculation of stress and deformation in fuel rod cladding during pellet-cladding interaction

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F00216305%3A26210%2F15%3APU124609" target="_blank" >RIV/00216305:26210/15:PU124609 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.14311/AP.2015.55.0384" target="_blank" >http://dx.doi.org/10.14311/AP.2015.55.0384</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.14311/AP.2015.55.0384" target="_blank" >10.14311/AP.2015.55.0384</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Calculation of stress and deformation in fuel rod cladding during pellet-cladding interaction

Popis výsledku v původním jazyce

The elementary parts of every fuel assembly, and thus of the reactor core, are fuel rods. The main function of cladding is hermetic separation of nuclear fuel from coolant. The fuel rod works in very specific and difficult conditions, so there are high requirements on its reliability and safety. During irradiation of fuel rods, a state may occur when fuel pellet and cladding interact. This state is followed by changes of stress and deformations in the fuel cladding. The article is focused on stress and deformation analysis of fuel cladding, where two fuels are compared: a fresh one and a spent one, which is in contact with cladding. The calculations are done for 4 different shapes of fuel pellets. It is possible to evaluate which shape of fuel pellet is the most appropriate in consideration of stress and deformation forming in fuel cladding, axial dilatation of fuel, and radial temperature distribution in the fuel rod, based on the obtained results.

Název v anglickém jazyce

Calculation of stress and deformation in fuel rod cladding during pellet-cladding interaction

Popis výsledku anglicky

The elementary parts of every fuel assembly, and thus of the reactor core, are fuel rods. The main function of cladding is hermetic separation of nuclear fuel from coolant. The fuel rod works in very specific and difficult conditions, so there are high requirements on its reliability and safety. During irradiation of fuel rods, a state may occur when fuel pellet and cladding interact. This state is followed by changes of stress and deformations in the fuel cladding. The article is focused on stress and deformation analysis of fuel cladding, where two fuels are compared: a fresh one and a spent one, which is in contact with cladding. The calculations are done for 4 different shapes of fuel pellets. It is possible to evaluate which shape of fuel pellet is the most appropriate in consideration of stress and deformation forming in fuel cladding, axial dilatation of fuel, and radial temperature distribution in the fuel rod, based on the obtained results.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

—

Návaznosti

O - Projekt operacniho programu

Rok uplatnění

2015

Kód důvěrnosti údajů

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

Název periodika

Acta Polytechnica

ISSN

1210-2709

e-ISSN

1805-2363

Svazek periodika

55

Číslo periodika v rámci svazku

6

Stát vydavatele periodika

CZ - Česká republika

Počet stran výsledku

4

Strana od-do

384-387

Kód UT WoS článku

000433701700005

EID výsledku v databázi Scopus

2-s2.0-84953306267