Multiscale Modeling of Radiation Damage in Oxide Dispersed Strengthened Steel Alloys: A Perspective

MM Azeem, I Jamil, MB Khan - International Journal of Engineering …, 2022 - hal.science
Currently, state-of-the-art reactors concept is based upon higher efficiency and better
utilization of nuclear power. This energy is considered an alternate source replacing …

Radiation damage effects in oxide dispersion strengthened steel alloys

MM Azeem, M Zubair, M Ado… - The Proceedings of …, 2019 - jstage.jst.go.jp
Oxide dispersed strengthened steel (ODSS) is widely used in nuclear industry due to its
excellent creep and void swelling resistance. The presence of high density of uniformly …

Molecular dynamics studies and irradiation effects in ODSS alloys

MM Azeem, Z Li, Q Wang… - International Journal of …, 2018 - inderscienceonline.com
Radiation Damage (RD) studies on structural materials provide a way to understand a
material's behaviour in a NPP. Oxide Dispersed Strengthened Steel (ODSS) alloys have …

Simulating radiation effects in iron with embedded oxide nanoparticles

T Lazauskas - 2014 - repository.lboro.ac.uk
Alloys used in fission and in future fusion reactors are subjected to extreme conditions
including high temperatures, corrosive and intense radiation environments. Understanding …

Mechanical behavior of oxide dispersion strengthened steels irradiated in JOYO

S Yamashita, T Yoshitake, N Akasaka, S Ukai… - Materials …, 2005 - jstage.jst.go.jp
Oxide dispersion strengthened (ODS) steels are highly regarded as candidate structural
materials for the demonstration fusion (DEMO) reactor which will be built next to the …

[图书][B] Microstructural and mechanical characterization of radiation effects in model reactor pressure vessel steels

A Ulbricht, J Böhmert, HW Viehrig - 2005 - books.google.com
This paper presents results of radiation-induced nanoscale microstructural changes
measured by Small-Angle Neutron Scattering (SANS) on ASTM-type reactor pressure vessel …

Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature

TR Allen, D Kaoumi, JP Wharry, Z Jiao… - Journal of Materials …, 2015 - cambridge.org
Designing materials for performance in high-radiation fields can be accelerated through a
carefully chosen combination of advanced multiscale modeling paired with appropriate …

Irradiation effects of Fe-Cr alloys

SA Ibrahim, Q Wang, M Ado, MM Azeem… - The Proceedings of the …, 2019 - jstage.jst.go.jp
Various researches have indicated the relative advantages of ferritic/martensitic (FM) steels
over austenitic and other steels currently in use in light water reactors, and have regarded …

Multi-scale modelling of irradiation effects in nuclear power plant materials

L Malerba - Understanding and Mitigating Ageing in Nuclear Power …, 2010 - Elsevier
This chapter surveys the computer-based multi-scale modelling approaches currently being
used to develop physical models of the effects of radiation on nuclear materials. The focus is …

Molecular dynamics simulations of damage cascades creation in oxide-particle-embedded Fe

AM Mustafa, Z Li, L Shao - International …, 2017 - asmedigitalcollection.asme.org
Oxide-dispersion-strengthened (ODS) alloys have been identified as one promising
candidate alloy type for high temperature reactor applications. Understanding irradiation …