Radiation damage in nanostructured materials
Materials subjected to high dose irradiation by energetic particles often experience severe
damage in the form of drastic increase of defect density, and significant degradation of their …
damage in the form of drastic increase of defect density, and significant degradation of their …
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 …
research, focusing on predicting ductile-to-brittle transition temperature shifts (ΔT), along …
[HTML][HTML] Sequential nucleation of phases in a 17-4PH steel: Microstructural characterisation and mechanical properties
A major concern for 17-4PH steels operating at elevated temperatures is embrittlement due
to Fe-rich (α) and Cr-enriched (α′) phase separation, along with precipitation of other …
to Fe-rich (α) and Cr-enriched (α′) phase separation, along with precipitation of other …
Solute diffusion by self-interstitial defects and radiation-induced segregation in ferritic Fe–X (X= Cr, Cu, Mn, Ni, P, Si) dilute alloys
This work investigates solute transport due to self-interstitial defects and radiation induced
segregation tendencies in dilute ferritic alloys, by computing the transport coefficients of …
segregation tendencies in dilute ferritic alloys, by computing the transport coefficients of …
Flux effects in precipitation under irradiation–Simulation of Fe-Cr alloys
Radiation-enhanced precipitation of Cr-rich α′ in irradiated Fe-Cr alloys, which results in
hardening and embrittlement, depends on the irradiating particle and the displacement per …
hardening and embrittlement, depends on the irradiating particle and the displacement per …
Precipitation in reactor pressure vessel steels under ion and neutron irradiation: On the role of segregated network dislocations
GR Odette, N Almirall, PB Wells, T Yamamoto - Acta Materialia, 2021 - Elsevier
The ultrahigh density of Mn-Ni-Si-Cu precipitates that form in irradiated reactor pressure
vessels (RPV) result in hardening and embrittlement, which may limit the service life of aging …
vessels (RPV) result in hardening and embrittlement, which may limit the service life of aging …
Precipitation and hardening in irradiated low alloy steels with a wide range of Ni and Mn compositions
N Almirall, PB Wells, T Yamamoto, K Wilford, T Williams… - Acta Materialia, 2019 - Elsevier
Abstract Mn-Ni-Si intermetallic precipitates (MNSPs) that are observed in some Fe-based
alloys following thermal aging and irradiation are of considerable scientific and technical …
alloys following thermal aging and irradiation are of considerable scientific and technical …
The effect of phosphorus on precipitation in irradiated reactor pressure vessel (RPV) steels
Embrittlement of light water reactor pressure vessel (RPV) steels by fast neutron irradiation
may limit extended nuclear plant life. Embrittlement, which is manifested as increases in …
may limit extended nuclear plant life. Embrittlement, which is manifested as increases in …
Thermodynamic and kinetic modeling of Mn-Ni-Si precipitates in low-Cu reactor pressure vessel steels
Formation of large volume fractions of Mn-Ni-Si precipitates (MNSPs) causes excess
irradiation embrittlement of reactor pressure vessel (RPV) steels at high, extended-life …
irradiation embrittlement of reactor pressure vessel (RPV) steels at high, extended-life …
Systematic electronic-structure investigation of substitutional impurity diffusion and flux coupling in bcc iron
The diffusion properties of a wide range of impurities (transition metals and Al, Si, and P) in
ferritic alloys are here investigated by means of a combined ab initio–atomic diffusion theory …
ferritic alloys are here investigated by means of a combined ab initio–atomic diffusion theory …