Effect of neutron irradiation on tensile properties of materials for pressure vessel internals of WWER type reactors

Studies in large plastic flow and fracture

R. Hill · Journal of the Mechanics and Physics of Solids · 1953 · 1K citations

Engineering, Petroleum Engineering, Fluid Dynamics +10

Deformation mechanisms in 316 stainless steel irradiated at 60°C and 330°C

Naoyuki Hashimoto, S.J. Zinkle, A.F. Rowcliffe et al. · Journal of Nuclear Materials · 2000 · 89 citations

Natural Sciences, Materials Engineering, Materials Science +14

Improved probabilistic model for fracture toughness prediction for nuclear pressure vessel steels

A. G. Gulenko · International Journal of Pressure Vessels and Piping · 1998 · 78 citations

Engineering, Materials Engineering, Materials Science +16

Fast neutron irradiation hardening of austenitic stainless steel at 250°C

J. D. Elen, P. Fenici · Journal of Nuclear Materials · 1992 · 41 citations

Engineering, Materials Engineering, Materials Science +12

Radiation embrittlement modelling for reactor pressure vessel steels: I. Brittle fracture toughness prediction

A. G. Gulenko · International Journal of Pressure Vessels and Piping · 1999 · 33 citations

Engineering, Materials Engineering, Nuclear Engineering +16