Recent developments in irradiation-resistant steels

GR Odette, MJ Alinger, BD Wirth - Annu. Rev. Mater. Res., 2008 - annualreviews.org
Advanced fission and future fusion energy will require new high-performance structural
alloys with outstanding properties that are sustained under long-term service in ultrasevere …

Irradiation damage concurrent challenges with RAFM and ODS steels for fusion reactor first-wall/blanket: a review

A Bhattacharya, SJ Zinkle, J Henry… - Journal of Physics …, 2022 - iopscience.iop.org
Reduced activation ferritic martensitic (RAFM) and oxide dispersion strengthened (ODS)
steels are the most promising candidates for fusion first-wall/blanket (FW/B) structures. The …

[HTML][HTML] Current state and prospect on the development of advanced nuclear fuel system materials: A review

D Yun, C Lu, Z Zhou, Y Wu, W Liu, S Guo, T Shi… - Materials Reports …, 2021 - Elsevier
The intricate balance between reactor economics and safety necessitates the emergence of
new and advanced nuclear systems and, very importantly, advanced materials, which can …

Austenitic stainless steel strengthened by the in situ formation of oxide nanoinclusions

K Saeidi, L Kvetková, F Lofaj, Z Shen - Rsc Advances, 2015 - pubs.rsc.org
An austenitic stainless steel was prepared by laser melting. High resolution transmission
electron microscopy with energy dispersive spectrometry confirmed the in situ formation of …

[PDF][PDF] 1.06-The effects of helium in irradiated structural alloys

Y Dai, GR Odette, T Yamamoto - Comprehensive Nuclear …, 2012 - researchgate.net
MD Molecular dynamics MS Molecular statics NF Nanofeatures NFA Nanostructured ferritic
alloys ODE Ordinary differential equation OEMS(Positron) orbital electron momentum …

Correlation between chemical composition and size of very small oxide particles in the MA957 ODS ferritic alloy

H Sakasegawa, L Chaffron, F Legendre… - Journal of Nuclear …, 2009 - Elsevier
ODS (oxide dispersion strengthened) alloys have superior creep properties. As it is well
known, these excellent creep properties result from very fine oxide particles dispersed with …

Ion-induced swelling of ODS ferritic alloy MA957 tubing to 500 dpa

MB Toloczko, FA Garner, VN Voyevodin… - Journal of Nuclear …, 2014 - Elsevier
In order to study the potential swelling behavior of the ODS ferritic alloy MA957 at very high
dpa levels, specimens were prepared from pressurized tubes that were unirradiated …

Evaluation of Helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation

K Yutani, H Kishimoto, R Kasada, A Kimura - Journal of Nuclear materials, 2007 - Elsevier
Effects of ion-irradiation on the swelling behavior were investigated for a high-chromium
oxide dispersion strengthened (ODS) ferritic steel and a 9Cr–2W reduced-activation ferritic …

[HTML][HTML] Irradiation effects of HT-9 martensitic steel

Y Chen - Nuclear Engineering and Technology, 2013 - Elsevier
High-Cr martensitic steel HT-9 is one of the candidate materials for advanced nuclear
energy systems. Thanks to its excellent thermal conductivity and irradiation resistance …

Pre-and post-deformation microstructures of oxide dispersion strengthened ferritic steels

R Kasada, N Toda, K Yutani, HS Cho… - Journal of Nuclear …, 2007 - Elsevier
Pre-and post-deformation microstructures and tensile properties of the newly-developed
oxide dispersion strengthened (ODS) ferritic steels, K1 (Fe–19Cr–0.3 W–0.3 Ti–0.3 Y2O3) …