| Issue |
Section |
Title |
File |
| Vol 7, No 6 (2016) |
Structural–Technological Strenghts and Working Capacity of Materials |
Formulation of criteria and reasoning procedure for the safe operation of pipelines and FBR housings under conditions of sodium leakage via through crack and its combustion |
|
| Vol 7, No 6 (2016) |
Structural–Technological Strenghts and Working Capacity of Materials |
Initial data and criteria for the reasoning procedure for the safe operation of pipelines and housing of equipment of FBR under conditions of sodium leakage via through crack and its combustion |
|
| Vol 7, No 6 (2016) |
Radiation Material Science |
Assessment of the crack growth rate in the material of the VVER-1000 reactor internals under irradiation creep |
|
| Vol 8, No 6 (2017) |
Structural–Technological Strenghts and Working Capacity of Materials |
On calculation of the contour size of the J-integral for assessment of the structural integrity of the VVER reactor pressure vessels under emergency core cooling |
|
| Vol 8, No 6 (2017) |
Radiation Materials Science |
Prediction of radiation embrittlement of WWER-1000 reactor vessel materials considering the influence of alloying elements and high content of copper |
|
| Vol 9, No 6 (2018) |
Radiation Materials Science |
Synergistic Mechanism of Radiation Embrittlement of Austenitic Stainless Steels under Long-Term High-Temperature Irradiation |
|
| Vol 9, No 6 (2018) |
Radiation Materials Science |
Influence of Neutron Irradiation and Post-Irradiation Annealing on Mechanical Properties and Fracture Toughness of the Anticorrosive Cladding for VVER-Type Reactors: Part 1. Mechanisms of Embrittlement and Recovery of Cladding Properties |
|
| Vol 9, No 6 (2018) |
Radiation Materials Science |
Influence of Neutron Irradiation and Post-Irradiation Annealing on Mechanical Properties and Fracture Toughness of Anticorrosive Cladding for VVER-Type Reactors: Part 2. Predictive Modeling of the Mechanical Properties and Fracture Toughness of Cladding |
|
| Vol 9, No 6 (2018) |
Radiation Materials Science |
Study of Steel Corrosion Cracking Mechanisms for VVER RPV Internals Based on Simulation Tests |
|
| Vol 9, No 6 (2018) |
Structural and Technological Strength and Efficiency of Materials |
Construction of Theoretical Curves of the Long-Term Strength for Neutron-Irradiated Austenitic Steels Kh18N9 and 08Kh16N11M3 |
|
| Vol 10, No 6 (2019) |
Structural and Technological Strength and Efficiency of Materials |
The Basic Principles of Assessment of the Structural Integrity and Lifetime of the BN-Type Fast Neutron Reactor Components Considering Material Degradation |
|
