The Irradiation Effects in Ferritic, Ferritic–Martensitic and Austenitic Oxide Dispersion Strengthened Alloys: A Review

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68081723%3A_____%2F24%3A00587875" target="_blank" >RIV/68081723:_____/24:00587875 - isvavai.cz</a>

Výsledek na webu

<a href="https://www.mdpi.com/1996-1944/17/14/3409" target="_blank" >https://www.mdpi.com/1996-1944/17/14/3409</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.3390/ma17143409" target="_blank" >10.3390/ma17143409</a>

Jazyk výsledku

angličtina

Název v původním jazyce

The Irradiation Effects in Ferritic, Ferritic–Martensitic and Austenitic Oxide Dispersion Strengthened Alloys: A Review

Popis výsledku v původním jazyce

High-performance structural materials (HPSMs) are needed for the successful and safendesign of fission and fusion reactors. Their operation is associated with unprecedented fluxes ofnhigh-energy neutrons and thermomechanical loadings. In fission reactors, HPSMs are used, e.g.,nfor fuel claddings, core internal structural components and reactor pressure vessels. Even strongernrequirements are expected for fourth-generation supercritical water fission reactors, with a particularnfocus on the HPSM’s corrosion resistance. The first wall and blanket structural materials in fusionnreactors are subjected not only to high energy neutron irradiation, but also to strong mechanical,nheat and electromagnetic loadings. This paper presents a historical and state-of-the-art summarynfocused on the properties and application potential of irradiation-resistant alloys predominantlynstrengthened by an oxide dispersion. These alloys are categorized according to their matrix as ferritic,nferritic–martensitic and austenitic. Low void swelling, high-temperature He embrittlement, thermalnand irradiation hardening and creep are typical phenomena most usually studied in ferritic andnferritic martensitic oxide dispersion strengthened (ODS) alloys. In contrast, austenitic ODS alloysnexhibit an increased corrosion and oxidation resistance and a higher creep resistance at elevatedntemperatures. This is why the advantages and drawbacks of each matrix-type ODS are discussed innthis paper.

Název v anglickém jazyce

The Irradiation Effects in Ferritic, Ferritic–Martensitic and Austenitic Oxide Dispersion Strengthened Alloys: A Review

Popis výsledku anglicky

High-performance structural materials (HPSMs) are needed for the successful and safendesign of fission and fusion reactors. Their operation is associated with unprecedented fluxes ofnhigh-energy neutrons and thermomechanical loadings. In fission reactors, HPSMs are used, e.g.,nfor fuel claddings, core internal structural components and reactor pressure vessels. Even strongernrequirements are expected for fourth-generation supercritical water fission reactors, with a particularnfocus on the HPSM’s corrosion resistance. The first wall and blanket structural materials in fusionnreactors are subjected not only to high energy neutron irradiation, but also to strong mechanical,nheat and electromagnetic loadings. This paper presents a historical and state-of-the-art summarynfocused on the properties and application potential of irradiation-resistant alloys predominantlynstrengthened by an oxide dispersion. These alloys are categorized according to their matrix as ferritic,nferritic–martensitic and austenitic. Low void swelling, high-temperature He embrittlement, thermalnand irradiation hardening and creep are typical phenomena most usually studied in ferritic andnferritic martensitic oxide dispersion strengthened (ODS) alloys. In contrast, austenitic ODS alloysnexhibit an increased corrosion and oxidation resistance and a higher creep resistance at elevatedntemperatures. This is why the advantages and drawbacks of each matrix-type ODS are discussed innthis paper.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

20501 - Materials engineering

Projekt

<a href="/cs/project/GX21-02203X" target="_blank" >GX21-02203X: Vylepšení vlastností současných špičkových slitin</a><br>

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2024

Kód důvěrnosti údajů

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

Název periodika

Materials

ISSN

1996-1944

e-ISSN

1996-1944

Svazek periodika

17

Číslo periodika v rámci svazku

14

Stát vydavatele periodika

CH - Švýcarská konfederace

Počet stran výsledku

36

Strana od-do

3409

Kód UT WoS článku

001277532500001

EID výsledku v databázi Scopus

2-s2.0-85199808394