"VNIINM" named after AA Bochvar

Recent papers from "VNIINM" named after AA Bochvar

1. Elastic and Relaxation Properties of V and Low-Activated V–W–Cr, V–W–Cr–Zr, V–Ta–Cr–Zr, and V–4Cr–4Ti AlloysInorganic Materials Applied Research · 2026
2. Microstructure and hydrogen content of electrodeposited chromium coating on the inner surface of EP823-SH steel claddingNuclear Engineering and Design · 2026
3. On the Extraction of Trivalent f-Elements from High-Level Waste Containing Derivatives of (2-Carbamoylethyl) Diphenylphosphine OxidesInorganic Materials · 2025
4. Online Monitoring of Nitric Acid Concentration in Extraction Process Streams Using Raman SpectroscopyMoscow University Physics Bulletin · 2026
5. The Effect of Structural States on the Microstructure and Mechanical Properties of Low-Activation Austenitic Steel After Long-Term Thermal Exposure at 700 °CJournal of Manufacturing and Materials Processing · 2026
6. Models and Validation Results of the TRITIUM Module Used as Part of the EUCLID/V2 Integrated Code for Calculating the Tritium Behavior in Lead Cooled Fast Reactor SystemsThermal Engineering · 2026
7. Assessment of the Explosiveness of Dried Residues from Nitric Acid Solutions Containing Organic Reductants for Reprocessing of (U, Pu)N Spent Nuclear FuelRadiochemistry · 2026
8. Tritium Handling in the Tokamak with Reactor TechnologiesPhysics of Atomic Nuclei · 2025
9. Peculiarities of Dispersion Strengthening of V–Cr–W–Zr–(C, O, N) Alloy by ZrC Nanoparticles under Conditions of Phase Instability of Crystalline LatticePhysics of Atomic Nuclei · 2025
10. Nitrogen under cladding of fuel pins with mixed uranium-plutonium nitrideNuclear Energy and Technology · 2025
11. Analysis of Methods for Deposition of Barrier Coatings on Carbon Fiber for Metal Matrix CompositesInorganic Materials Applied Research · 2025
12. Irradiation Creep in Metals: Multiscale ModellingCrystallography Reports · 2025
13. Studying the Thermal Expansion of Cladding Tubes and Rods Made of Zr-1% Nb Alloy in the Temperature Range of 293–873 K (20–600°C) Using X-ray and Dilatometric Measurement TechniquesInorganic Materials Applied Research · 2025
14. Modern Trends in Spent Nuclear Fuel Reprocessing and Waste FractionationRussian Journal of General Chemistry · 2024
15. Tokamak Tritium Cycle System with Reactor TechnologiesPhysics of Atomic Nuclei · 2024
16. Fracture Parameters and Plasticity of the Zr–Nb–Sn–Fe Tubes with Different Hydrides Orientations during the Mechanical TestingPhysics of Atomic Nuclei · 2024
17. The Structure of Superconducting Layers in Wire Composites with Internal Tin Sources Depending on the Wire DiameterThe Physics of Metals and Metallography · 2024
18. Features of Low-Temperature Plasticity, Mechanisms of Plastic Deformation and Fracture of the V–Cr–W–ZrC Alloy in the Process of Toughness TestingPhysics of Atomic Nuclei · 2024
19. Influence of Annealing Temperature on the Microstructure Features and Microhardness of Carbide-Strengthened V–Cr–W–Zr AlloyPhysics of Atomic Nuclei · 2024
20. Pulsed radiofrequency plasma for cleaning ITER first mirrors with and without notch-filter and magnetic fieldFusion Engineering and Design · 2024