Thermomechanical assessment of fuel rod cladding made of zirconium alloy and silicon carbide material during reactivity-initiated accident

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F00216305%3A26210%2F18%3APU124953" target="_blank" >RIV/00216305:26210/18:PU124953 - isvavai.cz</a>

Výsledek na webu

<a href="http://dx.doi.org/10.1080/00295639.2017.1373518" target="_blank" >http://dx.doi.org/10.1080/00295639.2017.1373518</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1080/00295639.2017.1373518" target="_blank" >10.1080/00295639.2017.1373518</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Thermomechanical assessment of fuel rod cladding made of zirconium alloy and silicon carbide material during reactivity-initiated accident

Popis výsledku v původním jazyce

This paper presents a thermomechanical assessment of various types of fuel cladding during a reactivity-initiated accident (RIA) which is simulated by the finite element analysis program ANSYS. Four cladding concepts are analyzed; one concept considers currently used zirconium alloy and three concepts consider silicon carbide (SiC) material. The SiC claddings consist either of composite material or of a twolayered structure formed of SiC composite and monolithic SiC. Each cladding is analyzed for two states of nuclear fuel: fresh and high burnup. A gap that exists between fuel pellets and cladding in fresh state is either reduced or removed in a high burnup state. It was shown that zirconium cladding resists RIA conditions very well in fresh state, however, in high burnup state significant stress and plastic strain occur. The SiC cladding was shown to have many advantages over zirconium alloy. Nevertheless, its lower strength appears to be critical in RIA conditions when cladding needs to withstand exceeding loading after the fuel-cladding gap disappears due to the expansion of the fuel pellet.

Název v anglickém jazyce

Thermomechanical assessment of fuel rod cladding made of zirconium alloy and silicon carbide material during reactivity-initiated accident

Popis výsledku anglicky

This paper presents a thermomechanical assessment of various types of fuel cladding during a reactivity-initiated accident (RIA) which is simulated by the finite element analysis program ANSYS. Four cladding concepts are analyzed; one concept considers currently used zirconium alloy and three concepts consider silicon carbide (SiC) material. The SiC claddings consist either of composite material or of a twolayered structure formed of SiC composite and monolithic SiC. Each cladding is analyzed for two states of nuclear fuel: fresh and high burnup. A gap that exists between fuel pellets and cladding in fresh state is either reduced or removed in a high burnup state. It was shown that zirconium cladding resists RIA conditions very well in fresh state, however, in high burnup state significant stress and plastic strain occur. The SiC cladding was shown to have many advantages over zirconium alloy. Nevertheless, its lower strength appears to be critical in RIA conditions when cladding needs to withstand exceeding loading after the fuel-cladding gap disappears due to the expansion of the fuel pellet.

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

<a href="/cs/project/LO1202" target="_blank" >LO1202: NETME CENTRE PLUS</a><br>

Návaznosti

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

Rok uplatnění

2018

Kód důvěrnosti údajů

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

Název periodika

NUCLEAR SCIENCE AND ENGINEERING

ISSN

0029-5639

e-ISSN

1943-748X

Svazek periodika

189

Číslo periodika v rámci svazku

1

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

13

Strana od-do

69-81

Kód UT WoS článku

000426587700005

EID výsledku v databázi Scopus

2-s2.0-85036618658