High-temperature creep behavior of Cr-coated optimized ZIRLO cladding via inverse analysis based on finite element method

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F25%3A00385359" target="_blank" >RIV/68407700:21340/25:00385359 - isvavai.cz</a>

Výsledek na webu

<a href="https://doi.org/10.1016/j.nucengdes.2025.114383" target="_blank" >https://doi.org/10.1016/j.nucengdes.2025.114383</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.nucengdes.2025.114383" target="_blank" >10.1016/j.nucengdes.2025.114383</a>

Jazyk výsledku

angličtina

Název v původním jazyce

High-temperature creep behavior of Cr-coated optimized ZIRLO cladding via inverse analysis based on finite element method

Popis výsledku v původním jazyce

After the Fukushima accident, nuclear power plant operators have required technologies that can prevent or delay the progression of a severe accident. For this reason, accident tolerant fuel (ATF) is being developed in many countries. As a near-term (NT) ATF cladding, chrome-coated cladding is the leading technology. The properties of the chromium coating layer change depending on the manufacturing process. It is inappropriate to directly apply bulk chromium properties to Cr coating due to significant microstructural differences. Since the thickness of the coating layer is tens of micrometers, it is difficult to obtain the properties by conventional experimental methods. This study presents a comprehensive approach to evaluate the high-temperature creep behavior of Cr-coated Optimized ZIRLOTM (Opt. ZIRLO) nuclear fuel cladding. The finite element method (FEM)based fuel performance code MERCURY, developed by KAERI, was coupled with the commercial optimization tool ISIGHT to perform inverse analysis. Under the framework of the IAEA ATF-TS project, isothermal bust tests were conducted at two temperature levels (1080 K and 1180 K) with various internal pressure conditions. The high-temperature creep parameters for both the substrate and Cr coating layers as well as the effective parameter for a single-layer model were derived. The burst analysis using the derived properties showed good agreement with the burst test results. The analysis also confirmed the delayed start point of ballooning for the chrome-coated cladding.

Název v anglickém jazyce

High-temperature creep behavior of Cr-coated optimized ZIRLO cladding via inverse analysis based on finite element method

Popis výsledku anglicky

After the Fukushima accident, nuclear power plant operators have required technologies that can prevent or delay the progression of a severe accident. For this reason, accident tolerant fuel (ATF) is being developed in many countries. As a near-term (NT) ATF cladding, chrome-coated cladding is the leading technology. The properties of the chromium coating layer change depending on the manufacturing process. It is inappropriate to directly apply bulk chromium properties to Cr coating due to significant microstructural differences. Since the thickness of the coating layer is tens of micrometers, it is difficult to obtain the properties by conventional experimental methods. This study presents a comprehensive approach to evaluate the high-temperature creep behavior of Cr-coated Optimized ZIRLOTM (Opt. ZIRLO) nuclear fuel cladding. The finite element method (FEM)based fuel performance code MERCURY, developed by KAERI, was coupled with the commercial optimization tool ISIGHT to perform inverse analysis. Under the framework of the IAEA ATF-TS project, isothermal bust tests were conducted at two temperature levels (1080 K and 1180 K) with various internal pressure conditions. The high-temperature creep parameters for both the substrate and Cr coating layers as well as the effective parameter for a single-layer model were derived. The burst analysis using the derived properties showed good agreement with the burst test results. The analysis also confirmed the delayed start point of ballooning for the chrome-coated cladding.

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/TM04000018" target="_blank" >TM04000018: Společný kooperativní výzkum zaměřený na přenos technologických znalostí a kvalifikaci paliva odolného vůči haváriím pro nové jaderné elektrárny</a><br>

Návaznosti

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

Rok uplatnění

2025

Kód důvěrnosti údajů

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

Název periodika

Nuclear Engineering and Design

ISSN

0029-5493

e-ISSN

1872-759X

Svazek periodika

444

Číslo periodika v rámci svazku

12

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

13

Strana od-do

—

Kód UT WoS článku

001558116300002

EID výsledku v databázi Scopus

2-s2.0-105012934241