On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models

A dispersion strengthening model based on differing elastic moduli applied to the iron-copper system

Kathryn C Russell, L. M. Brown · Acta Metallurgica · 1972 · 466 citations

Natural Sciences, Materials Engineering, Materials Science +14

Recent progress in understanding reactor pressure vessel steel embrittlement

G.R. Odette, G.E. Lucas · Radiation effects and defects in solids · 1998 · 407 citations

Natural Sciences, Materials Engineering, Materials Science +17

Transmission electron microscope investigations of the structure of copper precipitates in thermally-aged Fe—Cu and Fe—Cu—Ni

P. J. Othen, M. L. Jenkins, George Smith et al. · Philosophical Magazine Letters · 1991 · 347 citations

Natural Sciences, Materials Engineering, Materials Science +16

Primary damage formation in bcc iron

R.E. Stoller, G.R. Odette, Brian D. Wirth · Journal of Nuclear Materials · 1997 · 294 citations

Engineering, Materials Engineering, Materials Science +4

On the dominant mechanism of irradiation embrittlement of reactor pressure vessel steels

G.R. Odette · Scripta Metallurgica · 1983 · 266 citations

Engineering, Materials Science, Nuclear Engineering +16