[HTML][HTML] The Irradiation Effects in Ferritic, Ferritic–Martensitic and Austenitic Oxide Dispersion Strengthened Alloys: A Review

N Luptáková, J Svoboda, D Bártková, A Weiser… - Materials, 2024 - mdpi.com
High-performance structural materials (HPSMs) are needed for the successful and safe
design of fission and fusion reactors. Their operation is associated with unprecedented …

Tailoring microstructure of austenitic stainless steel with improved performance for generation-IV fast reactor application: a review

S Chen, A Xie, X Lv, S Chen, C Yan, H Jiang, L Rong - Crystals, 2023 - mdpi.com
Austenitic stainless steels are selected as candidate materials for in-core and out-of-core
components of Generation-IV fast reactors due to their excellent operating experience in …

Meso-timescale atomistic simulations on coalescence process of He bubbles in Fe by SEAKMC method

Y Yamamoto, S Hayakawa, T Okita, M Itakura - Computational Materials …, 2023 - Elsevier
He bubbles are characteristic microstructures under fusion reactor conditions. They
approach and coalesce through their own migration, which significantly impacts the …

The effects of loop size on the unfaulting of Frank loops in heavy ion irradiation

D Chen, K Murakami, K Dohi, K Nishida, Z Li… - Journal of Nuclear …, 2020 - Elsevier
When stainless steels are exposed to high irradiation dose, a fraction of Frank loops will
unfault and transform into perfect loops. After unfaulting, perfect loops can glide and impinge …

Production, microstructure and mechanical properties of two different austenitic ODS steels

T Gräning, M Rieth, J Hoffmann, A Möslang - Journal of nuclear materials, 2017 - Elsevier
This article is to summarize and examine processing parameters of novel developed
austenitic oxide dispersed strengthened (ODS) steels. Comparing hot-rolled and extruded …

A study of the effect of titanium on the void swelling behavior of D9 steels by ion beam simulation

C David, BK Panigrahi, S Balaji… - Journal of Nuclear …, 2008 - Elsevier
The void swelling behavior of D9 with 0.25 Ti and D9 with 0.15 Ti modified steels was
studied using heavy ion irradiation. The cold worked samples were pre-implanted with a …

Molecular dynamic simulations evaluating the effect of the stacking fault energy on defect formations in face-centered cubic metals subjected to high-energy particle …

S Terayama, Y Iwase, S Hayakawa, T Okita… - Computational Materials …, 2021 - Elsevier
Austenitic stainless steels, which are used as incore structural materials in light water
reactors, are characterized by an extremely low stacking fault energy (SFE) among face …

Digital twin of artifact systems: models assimilated with monitoring data from material microstructures to social systems

T Okita, T Kawabata, H Murayama… - International Journal of …, 2020 - jstage.jst.go.jp
In contemporary society, where changes in the environment surrounding artifacts as well as
changes in the purpose and operating conditions of artifacts occur frequently, it is necessary …

Microstructural investigation of an extruded austenitic oxide dispersion strengthened steel containing a carbon-containing process control agent

T Gräning, M Rieth, J Hoffmann, S Seils… - Journal of Nuclear …, 2019 - Elsevier
The adhesion of austenitic oxide dispersion strengthened (ODS) steel during mechanical
alloying and a decreased powder production yield can be overcome by the addition of a …

Formation of Ni–Si clusters and their relationship with dislocation loops in irradiated stainless steels

D Chen, K Murakami, K Dohi, K Nishida, L Chen… - Journal of Nuclear …, 2023 - Elsevier
Ni–Si cluster is a major contributor to the irradiation hardening in irradiated stainless steels.
The heterogeneous nucleation of Ni–Si clusters is associated with radiation-induced …