High-temperature embrittlement of ferritic ODS steels in Pb/Pb-Bi coolants
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68081723%3A_____%2F12%3A00385479" target="_blank" >RIV/68081723:_____/12:00385479 - isvavai.cz</a>
Result on the web
—
DOI - Digital Object Identifier
—
Alternative languages
Result language
angličtina
Original language name
High-temperature embrittlement of ferritic ODS steels in Pb/Pb-Bi coolants
Original language description
The oxide dispersion strengthened steels (ODS) are consider as a structural material of the proposed future nuclear energy production systems developed: i) the generation IV fission reactors, ii) fusion reactors and iii) spallation neutron sources. Several of these future concepts foresee the use of lead-based coolant (lead-cooled fast reactor and spallation target), as well as for breeder carrying material (helium-cooled lithium-lead fusion reactor). Compatibility of structural materials working at thelimiting conditions in heavy liquid metal (Pb-based) environments is a very important issue. The embrittlement of the steel was explained by the porosity development and precipitates coarsening in the bulk of the steel and intercrystalline corrosion ofthe surface of the steel during long-time high-temperature exposition in liquid metals.
Czech name
—
Czech description
—
Classification
Type
O - Miscellaneous
CEP classification
JG - Metallurgy, metal materials
OECD FORD branch
—
Result continuities
Project
<a href="/en/project/GAP108%2F10%2F0466" target="_blank" >GAP108/10/0466: Fracture behaviour prediction based on kvantification of local material response</a><br>
Continuities
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Others
Publication year
2012
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů