The intergranular segregation of P atoms in steel is a major cause of nuclear pressure vessel (NPV) steel embrittlement. In this thesis, we have employed a range of computer simulation techniques to investigate radiation events, which take place in the NPV and their effect on the segregation of P atoms to the grain boundaries (GBs). Radiation events were simulated in a perfect bcc Fe lattice using the classical molecular dynamic technique. We have tested two recently developed interatomic potential models, a the second nearest-neighbour modified embedded atom method (2NN MEAM) and a new EAM potential against a conventional EAM potential for the simulation of displacement cascades. Radiation simulations in the energy range of 0.2–2 keV showe...
One of the key challenges to overcome when designing fusion reactors is choosing appropriate materia...
Symmetrical tilt and twist grain boundary structures have been simulated in bcc iron using a many-bo...
The purpose of this thesis is to improve predictions of irradiation hardening in metals with a focus...
The ageing state of the world's nuclear power infrastructure, and the need to reduce humanity s depe...
Il est bien connu que la ségrégation intergranulaire du phosphore peut diminuer la cohésion entre le...
It is well known that the intergranular segregation of phosphorus can diminish the cohesion between ...
Radiation can affect a material in many ways. Knowledge of this is vital in choosing the right mater...
Reactor pressure vessel steels are well-known to harden and embrittle under neutron irradiation, mai...
The study is aimed to understand atomic scale details of defect-boundary interactions, which are cri...
The evolution of materials at an atomistic level may have vital consequences for the properties of m...
International audienceLow-alloy ferritic steel (16MND5) is used for pressure vessels in French nucle...
Molecular dynamics techniques are used to explore metals at an atomic level. The focus of the studi...
As ferritic-martensitic (FM) steels receive increasing interest, due to the development of Generatio...
Austenitic stainless steels are commonly used materials for in-core components of nuclear light wate...
Austenitic stainless steels are commonly used materials for in-core components of nuclear light wate...
One of the key challenges to overcome when designing fusion reactors is choosing appropriate materia...
Symmetrical tilt and twist grain boundary structures have been simulated in bcc iron using a many-bo...
The purpose of this thesis is to improve predictions of irradiation hardening in metals with a focus...
The ageing state of the world's nuclear power infrastructure, and the need to reduce humanity s depe...
Il est bien connu que la ségrégation intergranulaire du phosphore peut diminuer la cohésion entre le...
It is well known that the intergranular segregation of phosphorus can diminish the cohesion between ...
Radiation can affect a material in many ways. Knowledge of this is vital in choosing the right mater...
Reactor pressure vessel steels are well-known to harden and embrittle under neutron irradiation, mai...
The study is aimed to understand atomic scale details of defect-boundary interactions, which are cri...
The evolution of materials at an atomistic level may have vital consequences for the properties of m...
International audienceLow-alloy ferritic steel (16MND5) is used for pressure vessels in French nucle...
Molecular dynamics techniques are used to explore metals at an atomic level. The focus of the studi...
As ferritic-martensitic (FM) steels receive increasing interest, due to the development of Generatio...
Austenitic stainless steels are commonly used materials for in-core components of nuclear light wate...
Austenitic stainless steels are commonly used materials for in-core components of nuclear light wate...
One of the key challenges to overcome when designing fusion reactors is choosing appropriate materia...
Symmetrical tilt and twist grain boundary structures have been simulated in bcc iron using a many-bo...
The purpose of this thesis is to improve predictions of irradiation hardening in metals with a focus...