Current development of body-centered cubic high-entropy alloys for nuclear applications
High-entropy alloys greatly expand the alloy design range and offer new possibilities for
improving material performance. Based on the worldwide research efforts in the last decade …
improving material performance. Based on the worldwide research efforts in the last decade …
Microstructural stability and mechanical behavior of FeNiMnCr high entropy alloy under ion irradiation
In recent years, high entropy alloys (HEAs) have attracted significant attention due to their
excellent mechanical properties and good corrosion resistance, making them potential …
excellent mechanical properties and good corrosion resistance, making them potential …
Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels
Three stainless steel alloys, high-purity 304 (HP304), high-purity 304 with high Si (HP304+
Si) and commercial purity 304 (CP304), were irradiated with 2MeV protons to a dose of 5dpa …
Si) and commercial purity 304 (CP304), were irradiated with 2MeV protons to a dose of 5dpa …
Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys
This paper provides an overview of advanced scanning transmission electron microscopy
(STEM) techniques used for characterization of irradiated BCC Fe-based alloys. Advanced …
(STEM) techniques used for characterization of irradiated BCC Fe-based alloys. Advanced …
Interactive effect of thermal aging and proton irradiation on microstructural evolution and hardening of δ-ferrite in 308L stainless steel weld metal
X Gao, X Lin, T Guo, L Xu, Y Han, B Jiang, X Mei… - Journal of Materials …, 2024 - Elsevier
In the harsh service environment of high temperature and intense neutron irradiation in
water-cooled nuclear reactors, the austenitic stainless steel weld overlay cladding on the …
water-cooled nuclear reactors, the austenitic stainless steel weld overlay cladding on the …
Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water
P Deng, Q Peng, EH Han, W Ke, C Sun, Z Jiao - Corrosion Science, 2017 - Elsevier
Abstract Effect of irradiation on corrosion of 304 nuclear grade stainless steel (304NG SS) in
simulated primary water of pressurized water reactor was investigated. The investigation …
simulated primary water of pressurized water reactor was investigated. The investigation …
Revealing the temperature-dependent hardening mechanisms of non-uniformly distributed defects for ion-irradiated metals: Experiments and modeling
In this work, an integrated approach including experimental examinations and theoretical
modeling was employed to examine the temperature-dependent hardening of structural …
modeling was employed to examine the temperature-dependent hardening of structural …
Ab-initio based modeling of diffusion in dilute bcc Fe–Ni and Fe–Cr alloys and implications for radiation induced segregation
A combination of ab-initio calculations and statistical mechanical models has been used to
study diffusion behavior in dilute ferritic Fe–Cr and Fe–Ni alloys. A full set of Onsager matrix …
study diffusion behavior in dilute ferritic Fe–Cr and Fe–Ni alloys. A full set of Onsager matrix …
Nanoindentation on ion irradiated steels
P Hosemann, C Vieh, RR Greco, S Kabra… - Journal of Nuclear …, 2009 - Elsevier
Radiation induced mechanical property changes can cause major difficulties in designing
systems operating in a radiation environment. Investigating these mechanical property …
systems operating in a radiation environment. Investigating these mechanical property …
Microstructure evolution of T91 irradiated in the BOR60 fast reactor
Microstructures of T91 neutron irradiated in the BOR60 reactor at five temperatures between
376° C and 524° C to doses between 15.4 and 35.1 dpa were characterized using …
376° C and 524° C to doses between 15.4 and 35.1 dpa were characterized using …