All Stories

  1. Microstructure-Informed Prediction of Hardening in Ion-Irradiated Reactor Pressure Vessel Steels
  2. Microstructural characterisation of brittle fracture initiation sites in reactor pressure vessel steels
  3. Microstructural Characterization of Reactor Pressure Vessel Steels
  4. Small-angle neutron scattering study of neutron-irradiated and post-irradiation annealed VVER-1000 reactor pressure vessel weld material
  5. Multiscale modelling in nuclear ferritic steels: From nano-sized defects to embrittlement
  6. Nanoindentation applied to ion-irradiated and neutron-irradiated Fe-9Cr and Fe-9Cr-NiSiP model alloys
  7. Small-angle neutron scattering uncovers irradiation effects on Fe-Cr model alloys and a steel
  8. Microstructure-informed prediction and measurement of nanoindentation hardness of an Fe-9Cr alloy irradiated with Fe-ions of 1 and 5 MeV energy
  9. Effect of Neutron Flux on an Irradiation-Induced Microstructure and Hardening of Reactor Pressure Vessel Steels
  10. Nanoindentation Response of Ion-Irradiated Fe, Fe-Cr Alloys and Ferritic-Martensitic Steel Eurofer 97: The Effect of Ion Energy
  11. Multiscale modelling for fusion and fission materials: The M4F project
  12. Depth distribution of irradiation-induced dislocation loops in an Fe-9Cr model alloy irradiated with Fe ions: The effect of ion energy
  13. Use of the small punch test for the estimation of ductile-to-brittle transition temperature shift of irradiated steels
  14. Microstructure and fracture toughness characterization of three 9Cr ODS EUROFER steels with different thermo-mechanical treatments
  15. The dominant mechanisms for the formation of solute-rich clusters in low-Cu steels under irradiation
  16. Relationships between depth-resolved primary radiation damage, irradiation-induced nanostructure and nanoindentation response of ion-irradiated Fe-Cr and ODS Fe-Cr alloys
  17. Microstructural characterization of inhomogeneity in 9Cr ODS EUROFER steel
  18. TEM Observation of Loops Decorating Dislocations and Resulting Source Hardening of Neutron-Irradiated Fe-Cr Alloys
  19. Nanoindentation of single- (Fe) and dual-beam (Fe and He) ion-irradiated ODS Fe-14Cr-based alloys: Effect of the initial microstructure on irradiation-induced hardening
  20. Effect of anisotropic microstructure of ODS steels on small punch test results
  21. Magnetic small-angle neutron scattering
  22. Post-irradiation annealing behaviour of oxide dispersion strengthened Fe-Cr alloys studied by nanoindentation
  23. Why Do Secondary Cracks Preferentially Form in Hot-Rolled ODS Steels in Comparison with Hot-Extruded ODS Steels?
  24. Helium-ion microscopy, helium-ion irradiation and nanoindentation of Eurofer 97 and ODS Eurofer
  25. Nanoindentation of ion-irradiated reactor pressure vessel steels – model-based interpretation and comparison with neutron irradiation
  26. Fe2+ ion irradiated JRQ steel investigated by nanoindentation and slow-positron Doppler broadening spectroscopy
  27. Microstructure characterization and strengthening mechanisms of oxide dispersion strengthened (ODS) Fe-9%Cr and Fe-14%Cr extruded bars
  28. The effect of the initial microstructure in terms of sink strength on the ion-irradiation-induced hardening of ODS alloys studied by nanoindentation
  29. Effect of microstructural anisotropy on fracture toughness of hot rolled 13Cr ODS steel – The role of primary and secondary cracking
  30. Investigation of spark plasma sintered oxide-dispersion strengthened steels by means of small-angle neutron scattering
  31. Alternative Fabrication Routes toward Oxide-Dispersion-Strengthened Steels and Model Alloys
  32. Fabrication and characterization of oxide dispersion strengthened (ODS) 14Cr steels consolidated by means of hot isostatic pressing, hot extrusion and spark plasma sintering
  33. Ion irradiation combined with nanoindentation as a screening test procedure for irradiation hardening
  34. JRQ and JPA irradiated and annealed reactor pressure vessel steels studied by positron annihilation
  35. Irradiation hardening of Fe–9Cr-based alloys and ODS Eurofer: Effect of helium implantation and iron-ion irradiation at 300 °C including sequence effects
  36. Effect of neutron flux on the characteristics of irradiation-induced nanofeatures and hardening in pressure vessel steels
  37. Bimodal Grain Size Distribution of Nanostructured Ferritic ODS Fe-Cr Alloys
  38. Contributions of Cu-rich clusters, dislocation loops and nanovoids to the irradiation-induced hardening of Cu-bearing low-Ni reactor pressure vessel steels
  39. Post-irradiation annealing behavior of neutron-irradiated FeCu, FeMnNi and FeMnNiCu model alloys investigated by means of small-angle neutron scattering
  40. FP7 Project LONGLIFE: Overview of results and implications
  41. Application of a three-feature dispersed-barrier hardening model to neutron-irradiated Fe–Cr model alloys
  42. Microstructural and mechanical characterisation of ODS ferritic alloys produced by mechanical alloying and spark plasma sintering
  43. Critical assessment of Cr-rich precipitates in neutron-irradiated Fe–12at%Cr: Comparison of SANS and APT
  44. Damage accumulation in pure iron and high concentrated Fe–12.5 at% Cr alloy: comparison between object kinetic Monte Carlo and cluster dynamics
  45. Small-angle neutron scattering of low-Cu RPV steels neutron-irradiated at 255°C and post-irradiation annealed at 290°C
  46. Cr segregation on dislocation loops enhances hardening in ferritic Fe–Cr alloys
  47. Long Term Irradiation Phenomena in RPV Steels—The LONGLIFE Project
  48. Nanoscale characterization of ODS Fe–9%Cr model alloys compacted by spark plasma sintering
  49. Application of Positron Annihilation Spectroscopy to the Study of Irradiated Fe-Cr Alloys
  50. Influence of the copper impurity level on the irradiation response of reactor pressure vessel steels investigated by SANS
  51. Vibrational contribution to the thermodynamics of nanosized precipitates: vacancy–copper clusters in bcc-Fe
  52. Safety Monitoring of Materials and Components of Nuclear Power Plants
  53. Nanoclusters in bcc-Fe containing vacancies, copper and nickel: Structure and energetics
  54. Ion-irradiation-induced damage in Fe–Cr alloys characterized by nanoindentation
  55. Microstructure of oxide dispersion strengthened Eurofer and iron–chromium alloys investigated by means of small-angle neutron scattering and transmission electron microscopy
  56. Small-angle neutron scattering investigation of as-irradiated, annealed and reirradiated reactor pressure vessel weld material of decommissioned reactor
  57. Structure, energetics and thermodynamics of copper–vacancy clusters in bcc-Fe: An atomistic study
  58. Cluster Dynamics Study of Neutron Irradiation Induced Defects in Fe-12.5at%Cr Alloy
  59. The microstructure of neutron-irradiated Fe–Cr alloys: A small-angle neutron scattering study
  60. SANS investigation of a neutron-irradiated Fe–9at%Cr alloy
  61. Characterization of neutron-irradiated ferritic model alloys and a RPV steel from combined APT, SANS, TEM and PAS analyses
  62. On the correlation between irradiation-induced microstructural features and the hardening of reactor pressure vessel steels
  63. On the formation of mixed vacancy-copper clusters in neutron-irradiated Fe-Cu alloys
  64. SANS investigation of neutron-irradiated Fe-Cr alloys
  65. Comparative small-angle neutron scattering study of neutron-irradiated Fe, Fe-based alloys and a pressure vessel steel
  66. Cluster dynamics simulation of point defect clusters in neutron irradiated pure iron
  67. Mechanical Properties of Spark Plasma Sintered Fe-Cr Compacts Strengthened by Nanodispersed Yttria Particles
  68. Irradiation Damage and Embrittlement in RPV Steels Under the Aspect of Long Term Operation: Overview of the FP7 Project LONGLIFE
  69. Study of Metastable States of the Precipitates in Reactor Steels Under Neutron Irradiation
  70. Acceleration of irradiation hardening of low-copper reactor pressure vessel steel observed by means of SANS and tensile testing
  71. Estimation of the solubility limit of Cr in Fe at 300°C from small-angle neutron scattering in neutron-irradiated Fe–Cr alloys
  72. Ion-irradiation-induced damage of steels characterized by means of nanoindentation
  73. Flux dependence of cluster formation in neutron irradiated weld material - small-angle neutron scattering experiments and rate theory simulation
  74. Cluster Dynamics Simulation of Reactor Pressure Vessel Steels under Irradiation
  75. Investigation of the Damage Around a Crack Tip in Metals using Small Angle X-Ray Scattering
  76. Flux dependence of cluster formation in neutron-irradiated weld material
  77. Nature of defect clusters in neutron-irradiated iron-based alloys deduced from small-angle neutron scattering
  78. Small-angle neutron scattering study of neutron-irradiated iron and an iron–nickel alloy
  79. Indentation response of single-crystalline GaAs in the nano-, micro-, and macroregime
  80. SANS response of VVER440-type weld material after neutron irradiation, post-irradiation annealing and reirradiation
  81. Small-angle neutron scattering study of post-irradiation annealed neutron irradiated pressure vessel steels
  82. Deformation-induced small-angle scattering contrast in aluminium alloys
  83. Material-related fundamentals of cutting techniques for GaAs wafer manufacturing
  84. Scaling of self-similar long fatigue crack growth in aluminium alloys
  85. On the factors affecting the propagation of long fatigue cracks in thin-sheet wrought aluminium alloys
  86. Mapping of the rate-controlling steps for environment-assisted fatigue crack growth applied to the aluminium alloy 6013 T6
  87. The material-dependent variability of fatigue crack growth rates of aluminium alloys in the Paris regime
  88. Environment-sensitive fracture of aluminium alloy 6013
  89. Environment-sensitive fracture of aluminium alloy 6013
  90. A new approach to the correlation between the coefficient and the exponent in the power law equation of fatigue crack growth
  91. Influence of the depth position on the neutron embrittlement of the VVER reactor pressure vessel steel 15Cr2MoV(A) consequences for the assessment of reactor safety
  92. The role of microstructure in the propagation of ultrasound in bainitic low-alloy steels
  93. Mechanisms of ultrasonic attenuation in a bainitic low-alloy steel