Safe and long term operation of nuclear reactors is one of the most discussed challenges in
nuclear power engineering. The radiation degradation of nuclear design materials limits the …

Irradiation induced microstructural changes in the NF709 austenitic stainless steel were
investigated under 1 MeV Kr ion irradiations to a dose of 3 dpa at room temperature (RT) …

Well known for its good weldability by conventional welding techniques and also for its strain
hardening ability, titanium stabilized austenitic stainless steel (AISI 321) thick tube in a …

Stainless steels are well known by their corrosion resistance. The austenitic types, in
particular, are also applied as structural components in engineering systems operating at …

Abstract 9Cr ferritic/martensitic steels are promising materials for in-core components in
advanced Gen-IV reactors. In these applications, their long-term microstructural stability …

One of the most important parameters in the design of the fusion‐fission hybrid reactor is the
selection of the first wall material. Because the oxide dispersion‐strengthened (ODS) steel …

Thin-walled tubes of austenitic stainless steel TP321 preferred for nuclear steam generator
applications were used to fabricate butt joint using Tungsten inert gas (TIG) welding process …

Composite powders of pre-alloyed 316 L austenitic stainless steel with yttria (Y2O3) powder
in various compositions (0.3, 1.0, 1.5 and 2 wt%) were synthesized by mechanical alloying …

Two distinct AISI type 316 stainless steels, of Brazilian and Swedish origins, were compared
regarding their creep fracture mechanisms at 600, 700 and 800° C. The possible …

The mechanical behavior and the strengthening mechanism of stainless steel welded joints
at 600° C have been investigated. The welds were composed of AISI 304 stainless steel, as …