Experimental study of damaged cr-coated fuel cladding in post-accident conditions

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21220%2F20%3A00364806" target="_blank" >RIV/68407700:21220/20:00364806 - isvavai.cz</a>

Výsledek na webu

<a href="https://doi.org/10.14311/APP.2020.28.0001" target="_blank" >https://doi.org/10.14311/APP.2020.28.0001</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.14311/APP.2020.28.0001" target="_blank" >10.14311/APP.2020.28.0001</a>

Jazyk výsledku

angličtina

Název v původním jazyce

Experimental study of damaged cr-coated fuel cladding in post-accident conditions

Popis výsledku v původním jazyce

To enhance the safety of nuclear power, the focus of researchers all around the world has recently mainly objected on the development of Accident Tolerant Fuels. Especially the Chromium coating of current Zirconium based cladding has been widely suggested and discussed for its immense positive effect on overall cladding properties. Nevertheless, it was observed that during the first stage of the Loss of Coolant Accident, cracks appear in the Cr coating due to its inability to tolerate higher plastic strain. Therefore, experimental methodology used in this article focuses on testing fuel cladding with damaged Cr coating after the high-temperature transient. The impact of cracks on degradation of cladding mechanical properties was observed using optical microscopy, ring compression test, microhardness, and evaluating hydrogen content and weight gain.

Název v anglickém jazyce

Experimental study of damaged cr-coated fuel cladding in post-accident conditions

Popis výsledku anglicky

To enhance the safety of nuclear power, the focus of researchers all around the world has recently mainly objected on the development of Accident Tolerant Fuels. Especially the Chromium coating of current Zirconium based cladding has been widely suggested and discussed for its immense positive effect on overall cladding properties. Nevertheless, it was observed that during the first stage of the Loss of Coolant Accident, cracks appear in the Cr coating due to its inability to tolerate higher plastic strain. Therefore, experimental methodology used in this article focuses on testing fuel cladding with damaged Cr coating after the high-temperature transient. The impact of cracks on degradation of cladding mechanical properties was observed using optical microscopy, ring compression test, microhardness, and evaluating hydrogen content and weight gain.

Druh

D - Stať ve sborníku

CEP obor

—

OECD FORD obor

20506 - Coating and films

Projekt

—

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2020

Kód důvěrnosti údajů

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

Název statě ve sborníku

ŠIMÁNĚ 2020: Student Conference on Nuclear Engineering

ISBN

978-80-01-06794-9

ISSN

—

e-ISSN

2336-5382

Počet stran výsledku

7

Strana od-do

1-7

Název nakladatele

České vysoké učení technické v Praze

Místo vydání

Praha

Místo konání akce

Praha

Datum konání akce

23. 6. 2020

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

000855082500001