Development of reduced-activation and radiation-resistant high-entropy alloys for fusion reactor

H Yang, Z Shao, Q Lu, C Cui, L Xu, G Yang - International Journal of …, 2024 - Elsevier
With the development of advanced nuclear reactors such as fusion reactors and Generation
IV reactors, structural materials for nuclear applications will face increasingly extreme …

[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 …

Managing the heat: in-vessel components

J Cane, A Barth, J Farrington… - Philosophical …, 2024 - royalsocietypublishing.org
The Spherical Tokamak for Energy Production (STEP) programme aims to deliver a first-of-a-
kind fusion prototype powerplant (SPP). The SPP plasma places extreme heat, particle and …

FENDL: A library for fusion research and applications

G Schnabel, DL Aldama, T Bohm, U Fischer… - Nuclear Data …, 2024 - Elsevier
Abstract The Fusion Evaluated Nuclear Data Library (FENDL) is a comprehensive and
validated collection of nuclear cross section data coordinated by the International Atomic …

[HTML][HTML] Dose and compositional dependence of irradiation-induced property change in FeCr

K Song, D Sheyfer, K Mizohata, M Zhang, W Liu… - Journal of Nuclear …, 2024 - Elsevier
Ferritic/martensitic steels will be used as structural components in next generation nuclear
reactors. Their successful operation relies on an understanding of irradiation-induced defect …

Machine learning-based predictions of yield strength for neutron-irradiated ferritic/martensitic steels

NJ Sai, P Rathore, K Sridharan, A Chauhan - Fusion Engineering and …, 2023 - Elsevier
Due to their superior resistance to radiation-induced damage, Ferritic/Martensitic (F/M)
steels are promising structural materials for advanced nuclear reactors. This study …

Evaluation of the interaction between SiC, pre-oxidized FeCrAlMo with aluminized and pre-oxidized Fe-8Cr-2W in flowing PbLi

M Romedenne, Y Zhang, YF Su, B Pint - Journal of Nuclear Materials, 2023 - Elsevier
Dissimilar materials interactions are a major concern when liquid metals are used as a
working fluid. To simulate a dual-coolant PbLi blanket, chemical vapor deposited (CVD) SiC …

[HTML][HTML] APT characterization of irradiation effects on MX phase in reduced-activation ferritic/martensitic steels

L Cui, Y Dai, SSA Gerstl, MA Pounchon - Journal of Nuclear Materials, 2023 - Elsevier
Reduced activation ferritic/martensitic steels (RAFMs), such as Eurofer 97 and F82H, are
designed to enhance the high-temperature strength by forming the fine dispersive particles …

Micromechanical characterization of a reduced-activation ferritic/martensitic steel by instrumented indentation and scratch methods

M Liu, Z Xu, H Fu, P Li - Fusion Engineering and Design, 2023 - Elsevier
Micromechanical properties of a reduced-activation ferritic/martensitic steel CLF-1 were
characterized by nanoindentation tests with Berkovich indenter, microhardness tests with …

[HTML][HTML] Simulations of radiation damage accumulation in Fe-9Cr under pulsed irradiation conditions representative of inertial fusion energy

S He, BD Wirth, L Snead, JR Trelewicz, Y Katoh… - Journal of Nuclear …, 2024 - Elsevier
Structural materials for laser-based inertial fusion energy (IFE) reactor concepts are
expected to operate under pulsed irradiation conditions, with cycles consisting of …