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

The result's identifiers

  • Result code in 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>

  • Result on the web

    <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>

Alternative languages

  • Result language

    angličtina

  • Original language name

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

  • Original language description

    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.

  • Czech name

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • OECD FORD branch

    20501 - Materials engineering

Result continuities

  • Project

    <a href="/en/project/GX21-02203X" target="_blank" >GX21-02203X: Beyond properties of current top performance alloys</a><br>

  • Continuities

    I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Others

  • Publication year

    2024

  • Confidentiality

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

Data specific for result type

  • Name of the periodical

    Materials

  • ISSN

    1996-1944

  • e-ISSN

    1996-1944

  • Volume of the periodical

    17

  • Issue of the periodical within the volume

    14

  • Country of publishing house

    CH - SWITZERLAND

  • Number of pages

    36

  • Pages from-to

    3409

  • UT code for WoS article

    001277532500001

  • EID of the result in the Scopus database

    2-s2.0-85199808394