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Overview of Intergranular Fracture of Neutron Irradiated Austenitic Stainless Steels

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F17%3AN0000020" target="_blank" >RIV/26722445:_____/17:N0000020 - isvavai.cz</a>

  • Result on the web

    <a href="https://www.mdpi.com/2075-4701/7/10/392/htm" target="_blank" >https://www.mdpi.com/2075-4701/7/10/392/htm</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.3390/met7100392" target="_blank" >10.3390/met7100392</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Overview of Intergranular Fracture of Neutron Irradiated Austenitic Stainless Steels

  • Original language description

    Austenitic stainless steels are normally ductile and exhibit deep dimples on fracture surfaces. These steels can, however, exhibit brittle intergranular fracture under some circumstances. The occurrence of intergranular fracture in the irradiated steels is briefly reviewed based on limited literature data. The data are sorted according to the irradiation temperature. Intergranular fracture may occur in association with a high irradiation temperature and void swelling. At low irradiation temperature, the steels can exhibit intergranular fracture at low or even at room temperatures during loading in air and in high temperature water (~300 °C). This paper deals with the similarities and differences for IG fractures and discusses the mechanisms involved. The intergranular fracture occurrence at low temperatures might be correlated with decohesion or twinning and strain martensite transformation in local narrow areas around grain boundaries. The possibility of a ductile-to-brittle transition is also discussed. In case of void swelling higher than 3%, quasi-cleavage at low temperature might be expected as a consequence of ductile-to-brittle fracture changes with temperature. Any existence of the change in fracture behavior in the steels of present thermal reactor internals with increasing irradiation dose should be clearly proven or disproven. Further studies to clarify the mechanism are recommended.

  • 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

    Result was created during the realization of more than one project. More information in the Projects tab.

  • Continuities

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

Others

  • Publication year

    2017

  • Confidentiality

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

Data specific for result type

  • Name of the periodical

    Metals

  • ISSN

    2075-4701

  • e-ISSN

  • Volume of the periodical

    7

  • Issue of the periodical within the volume

    10

  • Country of publishing house

    CH - SWITZERLAND

  • Number of pages

    21

  • Pages from-to

    1-21

  • UT code for WoS article

    000414846200009

  • EID of the result in the Scopus database

    2-s2.0-85030221650