PRECIPITATION OF OXIDE DISPERSION STRENGTH STEELS AFTER LONG-TERM ANNEALING AT TEMPERATURE OF 475 ° C

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F24%3A00378098" target="_blank" >RIV/68407700:21340/24:00378098 - isvavai.cz</a>

Výsledek na webu

<a href="https://doi.org/10.14311/AP.2024.64.0103" target="_blank" >https://doi.org/10.14311/AP.2024.64.0103</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.14311/AP.2024.64.0103" target="_blank" >10.14311/AP.2024.64.0103</a>

Jazyk výsledku

angličtina

Název v původním jazyce

PRECIPITATION OF OXIDE DISPERSION STRENGTH STEELS AFTER LONG-TERM ANNEALING AT TEMPERATURE OF 475 ° C

Popis výsledku v původním jazyce

Oxide dispersion strengthened steels are key alloys used in nuclear installations. Steels with chromium content of up to 10 wt % are suitable due to their advantageous properties and these alloys are used for the construction of technological devices in the primary circuit of nuclear power plants. From other studies, it can be concluded that chromium has anti -corrosive properties due to the formation of a passivation layer, which results in reduced activation of the material by thermal neutrons. Macroscopic properties are determined by their microstructure, and therefore, the description of the microstructure is important. Transmission M & ouml;ssbauer spectroscopy and atom probe tomography were used to characterise the material. This provides information about the physical and/or chemical environment of the resonant atoms can be obtained. Obtained spectral parameters reach saturation values from which the solubility limit of chromium in iron can be determined. In Cr -rich phase, the solubility limit can be estimated from the value of spectral parameters of the single -line in the spectrum annealed for the longest time. The suggested procedures are subsequently applied to the case studies of stainless steels suitable for the construction of various components of the III+/IV th generation of nuclear reactors (including fast and fusion reactors).

Název v anglickém jazyce

PRECIPITATION OF OXIDE DISPERSION STRENGTH STEELS AFTER LONG-TERM ANNEALING AT TEMPERATURE OF 475 ° C

Popis výsledku anglicky

Oxide dispersion strengthened steels are key alloys used in nuclear installations. Steels with chromium content of up to 10 wt % are suitable due to their advantageous properties and these alloys are used for the construction of technological devices in the primary circuit of nuclear power plants. From other studies, it can be concluded that chromium has anti -corrosive properties due to the formation of a passivation layer, which results in reduced activation of the material by thermal neutrons. Macroscopic properties are determined by their microstructure, and therefore, the description of the microstructure is important. Transmission M & ouml;ssbauer spectroscopy and atom probe tomography were used to characterise the material. This provides information about the physical and/or chemical environment of the resonant atoms can be obtained. Obtained spectral parameters reach saturation values from which the solubility limit of chromium in iron can be determined. In Cr -rich phase, the solubility limit can be estimated from the value of spectral parameters of the single -line in the spectrum annealed for the longest time. The suggested procedures are subsequently applied to the case studies of stainless steels suitable for the construction of various components of the III+/IV th generation of nuclear reactors (including fast and fusion reactors).

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

10301 - Atomic, molecular and chemical physics (physics of atoms and molecules including collision, interaction with radiation, magnetic resonances, Mössbauer effect)

Projekt

<a href="/cs/project/EF16_019%2F0000778" target="_blank" >EF16_019/0000778: Centrum pokročilých aplikovaných přírodních věd</a><br>

Návaznosti

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

Rok uplatnění

2024

Kód důvěrnosti údajů

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

Název periodika

Acta Polytechnica

ISSN

1210-2709

e-ISSN

1805-2363

Svazek periodika

64

Číslo periodika v rámci svazku

2

Stát vydavatele periodika

CZ - Česká republika

Počet stran výsledku

15

Strana od-do

103-117

Kód UT WoS článku

001229268600006

EID výsledku v databázi Scopus

2-s2.0-85205884193