Current phenomenological knowledge and understanding of mechanisms are reviewed for
radiation embrittlement of reactor pressure vessel low alloy steels and irradiation assisted …

Understanding the behavior of reactor pressure vessel (RPV) steels under irradiation is a
mandatory task that has to be elucidated in order to be able to operate safely a nuclear …

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 …

This paper presents an atom probe tomography study of phase transformation and solute
segregation in Fe–Cr alloys of low purity under self-ion irradiation. Fe–9% Cr and Fe–12 …

The microstructure of four neutron irradiated Fe–Cr model alloys of industrial purity (Fe–
2.5% Cr, Fe–5% Cr, Fe–9% Cr and Fe–12% Cr) has been characterized by atom probe …

The radiation embrittlement of low-alloyed reactor pressure vessel steels is partly due to the
formation of nanometer-sized solute clusters (Mn, Si, Ni, Cu and P). In order to determine if …

The embrittlement of reactor pressure vessel steels under neutron irradiation is partly due to
the formation of solute clusters. To gain more insight into their formation mechanisms, ferritic …

A solution annealed 304 and a cold worked 316 austenitic stainless steels were irradiated
from 0.36 to 5dpa at 350° C using 160keV Fe ions. Irradiated microstructures were …

We summarize the findings from an interlaboratory study conducted between ten
international research groups and investigate the use of the commonly used maximum …

A nanoscale description of the microstructure in a Fe–12at% Cr model alloy of low purity
which has been neutron irradiated at 300° C up to 0.6 dpa, has been performed owing to …