[HTML][HTML] Beryllium oxide utilized in nuclear reactors: Part II, A systematic review of the neutron irradiation effects
M Hou, X Zhou, B Liu - Nuclear Engineering and Technology, 2023 - Elsevier
Beryllium oxide (BeO) is being re-emphasized and utilized in Micro Modular Reactors
(MMR) because of its prominent nuclear and high temperature properties in recent years …
(MMR) because of its prominent nuclear and high temperature properties in recent years …
Microstructure response and lead-bismuth eutectic corrosion behavior of 11Cr1Si ferritic/martensitic steel after Au-ion irradiation
Q Chen, F Bai, P Wang, J Yang, C Zhu, W Zhang… - Corrosion …, 2022 - Elsevier
The effect of Au-ion irradiation dose on microstructure evolution and lead-bismuth eutectic
(LBE) corrosion behavior of 11Cr1Si ferritic/martensitic (F/M) steels was investigated. The …
(LBE) corrosion behavior of 11Cr1Si ferritic/martensitic (F/M) steels was investigated. The …
[HTML][HTML] Ion irradiation and examination of Additive friction stir deposited 316 stainless steel
This study explored solid-state additive friction stir deposition (AFSD) as a modular
manufacturing technology, with the aim of enabling a more rapid and streamlined on-site …
manufacturing technology, with the aim of enabling a more rapid and streamlined on-site …
Early corrosion behavior of low carbon 9Cr-ODS steel in high temperature oxygen-saturated lead-bismuth eutectic
C Yang, Y Xu, D Yun, B Zhao, W Liu, R Gao, S Xie… - Corrosion …, 2024 - Elsevier
The early corrosion behavior of low carbon 9Cr-ODS steel in 500° C oxygen-saturated LBE
was investigated. The thickness of the oxide film was found to increase with the duration of …
was investigated. The thickness of the oxide film was found to increase with the duration of …
Microstructure and magnetization evolution in bcc iron via direct first-principles predictions of radiation effects
E Mansouri, P Olsson - Physical Review Materials, 2023 - APS
We here model the radiation-induced microstructure evolution in bcc iron using the creation-
relaxation algorithm directly driven by density functional theory calculations and compare to …
relaxation algorithm directly driven by density functional theory calculations and compare to …
Multiscale Modeling of Radiation Damage in Oxide Dispersed Strengthened Steel Alloys: A Perspective
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 …
utilization of nuclear power. This energy is considered an alternate source replacing …
Irradiation response of innovatively engineered metastable TRIP high entropy alloy
Abstract Properties and radiation responses of a metastable high entropy alloy (HEA)
exhibiting the transformation induced plasticity (TRIP) effect were studied. Innovative …
exhibiting the transformation induced plasticity (TRIP) effect were studied. Innovative …
[HTML][HTML] Modeling of irradiation-induced microstructure evolution in Fe: Impact of Frenkel pair distribution
E Mansouri, P Olsson - Computational Materials Science, 2024 - Elsevier
This study investigated the irradiation-induced microstructure evolution in Fe, employing the
Creation-Relaxation Algorithm and different interatomic potentials. The influence of self …
Creation-Relaxation Algorithm and different interatomic potentials. The influence of self …
[HTML][HTML] Corrosion behaviour of 11Cr1Si ferritic/martensitic steel in static liquid lead–bismuth eutectic at 450–550℃
Q Chen, L Zhai, Y Chen, H Liu, J Yang… - Nuclear Materials and …, 2023 - Elsevier
The corrosion behaviour of 11Cr1Si ferritic/martensitic (F/M) steel in static liquid lead–
bismuth eutectic (LBE) at 450–550° C was investigated. The results show that the oxide …
bismuth eutectic (LBE) at 450–550° C was investigated. The results show that the oxide …
In-situ proton irradiation/lead-bismuth eutectic corrosion synergistic effect on corrosion behaviour of 11Cr1W1Si ferritic/martensitic steel
Q Chen, Y Chen, F Zhang, J Yang, C Zhu… - Journal of Nuclear …, 2023 - Elsevier
In-situ proton irradiation/lead-bismuth eutectic corrosion synergistic effect on corrosion
behaviour of 11Cr1W1Si ferritic/martensitic steel was investigated. The result indicated that …
behaviour of 11Cr1W1Si ferritic/martensitic steel was investigated. The result indicated that …