Qualification of L-DED 316L for Nuclear Reactor Core Applications – Material Characteristics Before and After Neutron Irradiation

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26316919%3A_____%2F25%3AN0000031" target="_blank" >RIV/26316919:_____/25:N0000031 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21340/25:00384332

Výsledek na webu

<a href="https://www.sciencedirect.com/science/article/pii/S173857332500333X?via%3Dihub" target="_blank" >https://www.sciencedirect.com/science/article/pii/S173857332500333X?via%3Dihub</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>

Jazyk výsledku

angličtina

Název v původním jazyce

Qualification of L-DED 316L for Nuclear Reactor Core Applications – Material Characteristics Before and After Neutron Irradiation

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

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.

Druh

J_imp - Článek v periodiku v databázi Web of Science

CEP obor

—

OECD FORD obor

20501 - Materials engineering

Projekt

—

Návaznosti

I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace

Rok uplatnění

2025

Kód důvěrnosti údajů

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

Název periodika

NUCLEAR ENGINEERING AND TECHNOLOGY

ISSN

1738-5733

e-ISSN

—

Svazek periodika

57

Číslo periodika v rámci svazku

11

Stát vydavatele periodika

KR - Korejská republika

Počet stran výsledku

11

Strana od-do

nestránkováno

Kód UT WoS článku

001525651500001

EID výsledku v databázi Scopus

2-s2.0-105009461359