ATF claddings after high-temperature steam oxidation: WDS and nanoindenta-tion studies to characterize in-depth material changes

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F22%3AN0000029" target="_blank" >RIV/26722445:_____/22:N0000029 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.journalmt.com/artkey/mft-202206-0003_atf-claddings-after-high-temperature-steam-oxidation-wds-and-nanoindentation-studies-to-characterize-in-depth.php" target="_blank" >https://www.journalmt.com/artkey/mft-202206-0003_atf-claddings-after-high-temperature-steam-oxidation-wds-and-nanoindentation-studies-to-characterize-in-depth.php</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.21062/mft.2022.078" target="_blank" >10.21062/mft.2022.078</a>

Jazyk výsledku

angličtina

Název v původním jazyce

ATF claddings after high-temperature steam oxidation: WDS and nanoindenta-tion studies to characterize in-depth material changes

Popis výsledku v původním jazyce

After the Fukushima accident in 2011 year, ATF nuclear fuel cladding concept was accelerated to achieve the reactor operation with the new accident tolerant structural materials. However, several designed solutions do not fulfil the accident tolerant concept but particularly increase the corrosion resistance of Zr-cladding tubes at normal operating conditions, so-called “Advanced Technology Fuel, EATF”. Cr-coated zirconium claddings following the first concept, have been the widely tested and the first full Cr-coated fuel rods have been planned to operate in LWR reactor conditions around the 2022 year. Our con-tribution describes the Cr-coated Zr-%1Nb cladding tube microstructure after high-temperature steam oxidation at 1200°C by means of Scanning Electron Microscopy and nanoindentation methods. The arti-cle is focused on WDS line-profile studies of oxygen and chromium diffusion into the Zr-matrix. The increased Cr-diffusion with oxygen is evident causing a change in local mechanical properties which is well-described by measurements of nanohardness and Young's modulus. In addition, the developed methodology of the WDS & nanoindentation line-analyses was also optimized to apply in hot-cell condi-tions to measure the effect of neutron-irradiation on the different coatings and coating/matrix interface.

Název v anglickém jazyce

ATF claddings after high-temperature steam oxidation: WDS and nanoindenta-tion studies to characterize in-depth material changes

Popis výsledku anglicky

After the Fukushima accident in 2011 year, ATF nuclear fuel cladding concept was accelerated to achieve the reactor operation with the new accident tolerant structural materials. However, several designed solutions do not fulfil the accident tolerant concept but particularly increase the corrosion resistance of Zr-cladding tubes at normal operating conditions, so-called “Advanced Technology Fuel, EATF”. Cr-coated zirconium claddings following the first concept, have been the widely tested and the first full Cr-coated fuel rods have been planned to operate in LWR reactor conditions around the 2022 year. Our con-tribution describes the Cr-coated Zr-%1Nb cladding tube microstructure after high-temperature steam oxidation at 1200°C by means of Scanning Electron Microscopy and nanoindentation methods. The arti-cle is focused on WDS line-profile studies of oxygen and chromium diffusion into the Zr-matrix. The increased Cr-diffusion with oxygen is evident causing a change in local mechanical properties which is well-described by measurements of nanohardness and Young's modulus. In addition, the developed methodology of the WDS & nanoindentation line-analyses was also optimized to apply in hot-cell condi-tions to measure the effect of neutron-irradiation on the different coatings and coating/matrix interface.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

20501 - Materials engineering

Projekt

<a href="/cs/project/TK03020169" target="_blank" >TK03020169: Prostředky a metodiky pro kvalifikaci „Accident Tolerant“ pokrytí jaderného paliva</a><br>

Návaznosti

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

Rok uplatnění

2022

Kód důvěrnosti údajů

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

Název periodika

Manufacturing Technology

ISSN

1213-2489

e-ISSN

2787-9402

Svazek periodika

22

Číslo periodika v rámci svazku

6

Stát vydavatele periodika

CZ - Česká republika

Počet stran výsledku

6

Strana od-do

703-708

Kód UT WoS článku

000908397300006

EID výsledku v databázi Scopus

2-s2.0-85146724558