Qualification of L-DED 316L for Nuclear Reactor Core Applications – Material Characteristics Before and After Neutron Irradiation in LVR-15 Research Reactor
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F25%3AN0000087" target="_blank" >RIV/26722445:_____/25:N0000087 - isvavai.cz</a>
Výsledek na webu
<a href="https://www.sciencedirect.com/science/article/pii/S173857332500333X" target="_blank" >https://www.sciencedirect.com/science/article/pii/S173857332500333X</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.net.2025.103765" target="_blank" >10.1016/j.net.2025.103765</a>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Qualification of L-DED 316L for Nuclear Reactor Core Applications – Material Characteristics Before and After Neutron Irradiation in LVR-15 Research Reactor
Popis výsledku v původním jazyce
The mechanical and microstructural properties of heat treated laser direct energy deposition (L-DED) fabricated austenitic stainless steel 316L were investigated before and after neutron irradiation in the LVR-15 research reactor dry capsule. Tensile tests were carried out at room temperature and elevated temperature followed by light optical microscopy (LOM) and scanning electron microscopy (SEM) analyses of the microstructure. The results showed that the L-DED material exhibited superior ultimate tensile strength (Rm) and yield strength (Rp0.2) mainly due to its smaller grain size (approximately 4x smaller), compared to conventionally manufactured steel. Despite promising mechanical properties, microstructure misorientation analyses revealed incomplete recrystallization after heat treatment, which may affect long-term performance under nuclear reactor conditions. However, no notable differences were observed in the material microstructure between conventionally fabricated and L- DED fabricated materials due to neutron radiation. These findings support the potential of not only laser-deposition but also AM in general as a viable technique for producing in-reactor components.
Název v anglickém jazyce
Qualification of L-DED 316L for Nuclear Reactor Core Applications – Material Characteristics Before and After Neutron Irradiation in LVR-15 Research Reactor
Popis výsledku anglicky
The mechanical and microstructural properties of heat treated laser direct energy deposition (L-DED) fabricated austenitic stainless steel 316L were investigated before and after neutron irradiation in the LVR-15 research reactor dry capsule. Tensile tests were carried out at room temperature and elevated temperature followed by light optical microscopy (LOM) and scanning electron microscopy (SEM) analyses of the microstructure. The results showed that the L-DED material exhibited superior ultimate tensile strength (Rm) and yield strength (Rp0.2) mainly due to its smaller grain size (approximately 4x smaller), compared to conventionally manufactured steel. Despite promising mechanical properties, microstructure misorientation analyses revealed incomplete recrystallization after heat treatment, which may affect long-term performance under nuclear reactor conditions. However, no notable differences were observed in the material microstructure between conventionally fabricated and L- DED fabricated materials due to neutron radiation. These findings support the potential of not only laser-deposition but also AM in general as a viable technique for producing in-reactor components.
Klasifikace
Druh
J<sub>imp</sub> - Článek v periodiku v databázi Web of Science
CEP obor
—
OECD FORD obor
20501 - Materials engineering
Návaznosti výsledku
Projekt
<a href="/cs/project/LM2023041" target="_blank" >LM2023041: České mezinárodní centrum výzkumných reaktorů</a><br>
Návaznosti
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Ostatní
Rok uplatnění
2025
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název periodika
Nuclear Engineering and Technology
ISSN
1738-5733
e-ISSN
1738-5733
Svazek periodika
57
Číslo periodika v rámci svazku
11
Stát vydavatele periodika
KR - Korejská republika
Počet stran výsledku
6
Strana od-do
1-6
Kód UT WoS článku
001525651500001
EID výsledku v databázi Scopus
2-s2.0-105009461359