Mechanical properties and microstructural stability of 11Cr-ferritic/martensitic steel cladding under irradiation

The in-reactor creep rupture tests of 11Cr-0.5Mo-2W, V, Nb F/M steel were carried out in the temperature range from 823 to 943 K using Materials Open Test Assembly in the Fast Flux Test Facility and tensile and temperature-transient-to-burst specimens were irradiated in the experimental fast reactor JOYO at temperatures between 693 and 1013 K to fast neutron doses ranging from 11 to 102 dpa. The results of post irradiation mechanical tests showed that there was no significant degradation in tensile and transient burst strengths even after neutron irradiation below 873 K, but that there was significant degradation in both strengths at neutron irradiation above 903 K. On the other hand, the in-reactor creep rupture times were equal or greater than those of out-reactor creep even after neutron irradiation at all temperatures. This creep rupture behavior was different from that of tensile and transient burst specimens

Effect of nitrogen concentration on nano-structure and high-temperature strength of 9Cr-ODS steel

The objective of this study was to investigate the effect of nitrogen concentration on mechanical properties and nano-structure of 9Cr oxide dispersion strengthened (ODS) ferritic/martensitic steel. 9Cr-ODS specimens with the wide range of nitrogen concentration, from 0.004 to 0.110 wt%, were systematically investigated by hardness and tensile tests and several microstructural characterization methods. Hardness and tensile strength at 973 K were significantly decreased as nitrogen concentration increased, due to the decrease in the amount of the residual α-ferrite phase. Coarse inclusions containing Y and Ti, which could negatively affect creep strength and processability, were formed, and that suggested degradation of the nano-particle distribution. The technical knowledge obtained in this study will contribute towards the setting of a reasonable nitrogen concentration specification for 9Cr-ODS steel. Keywords: ODS, Nitrogen, Ferrite, Martensite, α to γ reverse transformation, HT-XR

Strength anisotropy of rolled 11Cr-ODS steel

Materials for core components of fusion reactors and fast reactors, such as blankets and fuel cladding tubes, must offer the best possible high temperature strength and irradiation resistance because they will be exposed to high heat flux and heavy neutron irradiation. Japan Atomic Energy Agency (JAEA) has been developing 9 and 11 chromium (Cr) oxide dispersion strengthened (ODS) steels as candidate materials for advanced fast reactor cladding tubes. In this study the JAEA 11Cr-ODS steel was rolled in order to evaluate its anisotropy. The tensile tests and creep tests were carried out at 700°C in longitudinal and transverse orientations. The anisotropy of the tensile strength was negligible, though that of the creep strength was distinct. The observation results and chemical composition mapping suggested that the cause of the anisotropy in the creep strength was a previously formed columnar boundary, that is, a prior particle boundary including Ti-rich sub-micro metric precipitates

Effect of thermo-mechanical treatments on nano-structure of 9Cr-ODS steel

The effect of thermo-mechanical treatments (TMTs) on the evolution of nano-structure in an oxide dispersion strengthened (ODS) ferritic/martensitic steel (Fe-9Cr-2W-0.22Ti-0.36Y2O3) was investigated. TMTs involve hot extruding and subsequent forging, which are expected to be part of a future industrial-scale manufacturing process of the ODS steel. It was shown that the ODS steel was composed of two phases — a fine-grained residual ferrite phase and a transformable martensite phase. The number density of the nano-sized particles in the residual ferrite phase was significantly higher than that in the martensite phase. The TMTs did not significantly affect the number density, but slightly affected the size distribution of the nano-sized particles in both ferrite phase and martensite phase. Moreover, the volume fraction of the residual ferrite phase decreased after TMTs. In summary, the TMT conditions could be a parameter which affects the nano-structure of the ODS steel

Laser Beam Direct Energy Deposition of graded austenitic-to-martensitic steel junctions compared to dissimilar Electron Beam welding

International audienceThis article presents the Direct Metal Deposition (DMD) process as a method to build a graded austenitic-to-martensitic steel. Builds are obtained by varying the ratio of the two powders upon DMD processing. Samples with gradual transitions were successfully obtained thanks to the use of a high dilution rate from a layer to another. Long austenitic grains are observed on 316L side when martensitic grains are observed on Fe-9Cr-1Mo side. In the transition zone, the microstructure is mainly martensitic.Characterizations were performed after building and after a tempering heat treatment at 630°C during 8h and compared to dissimilar Electron Beam welds. Before heat treatment, DMD graded area has high hardness values (around 430 HV) due to fresh martensite formed during building. Tempering heat treatment allows reducing hardness in this area to 300 HV. EDS measurements indicate that the chemical gradient between 316L and Fe-9Cr-1Mo obtained by DMD is smoother than the chemical change obtained in Electron Beam (EB) welds. Microstructures in DMD are quite different from those obtained by EB welding. Hardness measurements in DMD samples and in welds exhibit similar behaviours: the weld metal and the Fe-9Cr-1Mo heat affected zone are relatively hard after welding because of fresh martensite, such as the DMD transition zone. These areas are all softened by the tempering heat treatment