On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models

GR Odette, T Yamamoto, TJ Williams… - Journal of Nuclear …, 2019 - Elsevier
This paper melds an overview of the history of Reactor Pressure Vessel (RPV) embrittlement
research, focusing on predicting ductile-to-brittle transition temperature shifts (ΔT), along …

Defect-specific strength factors and superposition model for predicting strengthening of ion irradiated Fe18Cr alloy

P Zhu, Y Zhao, YR Lin, J Henry, SJ Zinkle - Journal of Nuclear Materials, 2024 - Elsevier
A high-purity binary alloy Fe18Cr was subjected to heavy-ion irradiation in order to provide
improved understanding of the irradiation effect on radiation hardening associated with …

Effect of dose rate on dislocation loop evolution in tungsten: Combination of defect generation rate and elastic interaction

Y Ding, G Ran, Y Li, Z Cao, D Cui, J Huang, Z Zhou - Scripta Materialia, 2023 - Elsevier
Ion irradiation is often used to simulate neutron irradiation in reactor components, while the
dose rate discrepancy makes it difficult to directly compare ion irradiation with neutron …

Microstructural examination of neutron, proton and self-ion irradiation damage in a model Fe9Cr alloy

JC Haley, S de Moraes Shubeita, P Wady… - Journal of Nuclear …, 2020 - Elsevier
Transmission electron microscopy (TEM) was used to compare the microstructural defects
produced in an Fe9Cr model alloy during exposure to neutrons, protons, or self-ions …

Helical dislocations: Observation of vacancy defect bias of screw dislocations in neutron irradiated Fe–9Cr

JC Haley, F Liu, E Tarleton, ACF Cocks, GR Odette… - Acta Materialia, 2019 - Elsevier
We have analysed the microstructure of a model alloy of Fe9Cr irradiated with neutrons to a
dose of 1.6 dpa at 325° C. Helical dislocations comprise a major part of the damage; these …

Insights into Prismatic Loop Formation in Irradiated Fe–Cr Alloys from Hypothesis-Driven Active Learning and Causal Analysis

S Ghosh, A Tom, D Dasgupta, A Ghosh… - ACS Applied Energy …, 2024 - ACS Publications
Neutron and electron irradiation experimental studies conducted on body-centered cubic Fe
and Fe–Cr alloys have established two prismatic dislocation loop populations, which have …

[HTML][HTML] Macroscopic magnetic hardening due to nanoscale spinodal decomposition in Fe–Cr

V Vojtech, M Charilaou, A Kovács, A Firlus, SSA Gerstl… - Acta Materialia, 2022 - Elsevier
Abstract The Fe–Cr alloy system is the basis of ferritic steels, which are important structural
materials for many applications, including their use in future fusion reactors. However, when …

A data science approach for analysis and reconstruction of spinodal-like composition fields in irradiated FeCrAl alloys

Y Pachaury, T Kumagai, JP Wharry, A El-Azab - Acta Materialia, 2022 - Elsevier
A statistical method for the analysis of continuously distributed data representative of
composition fluctuations in irradiated FeCrAl alloys acquired using Energy Dispersive X-ray …

On the use of charged particles to characterize precipitation in irradiated reactor pressure vessel steels with a wide range of compositions

N Almirall, PB Wells, T Yamamoto, K Yabuuchi… - Journal of Nuclear …, 2020 - Elsevier
Nuclear reactor lifetimes may be limited by nano-scale Cu-Mn-Ni-Si precipitates (CRPs and
MNSPs) that form under neutron irradiation (NI) of pressure vessel (RPV) steels, resulting in …

Mechanical properties of FeCr alloys after neutron irradiation

MJ Konstantinović, L Malerba - Journal of Nuclear Materials, 2020 - Elsevier
The mechanical properties of neutron irradiated Fe–Cr ferritic model alloys with various
concentrations of Cr and minor solutes (Ni, Si and P) were investigated along with high-Cr …