Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors

G Jiang, D Xu, P Feng, S Guo, J Yang, Y Li - Journal of Alloys and …, 2021 - Elsevier
The safety of nuclear power plants has put forward new requirements for the corrosion
resistance of fuel cladding with the advancement of industrialization. FeCrAl alloys are …

Small scale mechanical testing of irradiated materials

P Hosemann, C Shin, D Kiener - Journal of Materials Research, 2015 - cambridge.org
Small specimen testing techniques have a long history in nuclear material research due to
the limitations posed by nuclear facilities. The limited space in reactors and the fact that the …

An in situ study on the effect of grain boundaries on helium bubble formation in dual beam irradiated FeCrAl alloy

T Sun, T Niu, Z Shang, WY Chen, M Li, H Wang… - Acta Materialia, 2023 - Elsevier
FeCrAl alloy is one of the promising cladding materials in the advanced nuclear reactors.
Here we compare the irradiation response of the nanolaminate (NL) and coarse-grained …

Effects of sequential tungsten and helium ion implantation on nano-indentation hardness of tungsten

DEJ Armstrong, PD Edmondson, SG Roberts - Applied Physics Letters, 2013 - pubs.aip.org
To simulate neutron and helium damage in a fusion reactor first wall sequential self-ion
implantation up to 13 dpa followed by helium-ion implantation up to 3000 appm was …

Research progress of ODS FeCrAl alloys–a review of composition design

X Wang, X Shen - Materials, 2023 - mdpi.com
After the Fukushima nuclear accident, the development of new accident-tolerant fuel
cladding materials has become a research hotspot around the world. Due to its outstanding …

Irradiation hardening of Fe–9Cr-based alloys and ODS Eurofer: Effect of helium implantation and iron-ion irradiation at 300 C including sequence effects

C Heintze, F Bergner, M Hernández-Mayoral… - Journal of Nuclear …, 2016 - Elsevier
Single-beam, dual-beam and sequential iron-and/or helium-ion irradiations are widely
accepted to emulate more application-relevant but hardly accessible irradiation conditions of …

Nanoindentation experiment and crystal plasticity study on the mechanical behavior of Fe-ion-irradiated A508-3 steel

P Lin, J Nie, M Liu - Journal of Nuclear Materials, 2022 - Elsevier
This study investigates the mechanical properties of A508-3 steel irradiated with Fe ions to
0.1, 0.4, 2.0, and 5.0 dpa at 20, 100, and 300° C using a nanoindentation experiment and …

A review of irradiation-induced hardening in FeCrAl alloy systems for accident-tolerant fuel cladding

A Tangirbergen, N Amangeldi, ST Revankar… - … Engineering and Design, 2024 - Elsevier
Despite nuclear energy being a clean, sustainable source, its safety is a major concern,
especially after the Chernobyl and Fukushima accidents. Designing accident-tolerant fuel …

Helium sequestration at nanoparticle-matrix interfaces in helium+ heavy ion irradiated nanostructured ferritic alloys

CM Parish, KA Unocic, L Tan, SJ Zinkle… - Journal of Nuclear …, 2017 - Elsevier
We irradiated four ferritic alloys with energetic Fe and He ions: one castable nanostructured
alloy (CNA) containing Ti-W-Ta-carbides, and three nanostructured ferritic alloys (NFAs) …

[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 …