Detail publikace
Thermomechanical assessment of fuel rod cladding made of zirconium alloy and silicon carbide material during reactivity-initiated accident
HALABUK, D. NÁVRAT, T.
Anglický název
Thermomechanical assessment of fuel rod cladding made of zirconium alloy and silicon carbide material during reactivity-initiated accident
Typ
článek v časopise ve Web of Science, Jimp
Jazyk
en
Originální abstrakt
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.
Anglický abstrakt
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.
Klíčová slova anglicky
reactivity-initiated accident, fuel cladding, finite element method
Vydáno
01.01.2018
Nakladatel
Taylor & Francis
Místo
New York
ISSN
0029-5639
Ročník
189
Číslo
1
Strany od–do
69–81
Počet stran
13
BIBTEX
@article{BUT140340,
author="Dávid {Halabuk} and Tomáš {Návrat},
title="Thermomechanical assessment of fuel rod cladding made of zirconium alloy and silicon carbide material during reactivity-initiated accident",
year="2018",
volume="189",
number="1",
month="January",
pages="69--81",
publisher="Taylor & Francis",
address="New York",
issn="0029-5639"
}