Tensile properties of modified 316 stainless steel (PNC316) after neutron irradiation over 100 dpa

A micromechanical analysis of swelling-induced embrittlement in neutron-irradiated austenitic stainless steels

(2022) J. Hure et al.   JOURNAL OF NUCLEAR MATERIALS

Study on the mechanism of diametral cladding strain and mixed-oxide fuel element breaching in slow-ramp extended overpower transients

(2012) Tomoyuki Uwaba et al.   JOURNAL OF NUCLEAR MATERIALS

Irradiation Performance of Fast Reactor MOX Fuel Assemblies Irradiated to High Burnups

(2012) Tomoyuki UWABA et al.   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

Swelling Behaviors in a Fuel Assembly for the Wrapping Wire and Duct Made of Modified 316 Austenitic Stainless Steel

(2012) Ichiro YAMAGATA et al.   JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY

Effect of neutron irradiation on the microstructure of modified SUS316 stainless steels

(2010) Shinichiro Yamashita et al.   JOURNAL OF NUCLEAR MATERIALS

Severe embrittlement of neutron irradiated austenitic steels arising from high void swelling

(2008) V.S. Neustroev et al.   JOURNAL OF NUCLEAR MATERIALS