279 results on '"A, Kiselev"'
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2. Load Effects Inside NPP VVER-1000 Containment Wall Cross Section
3. Radiation Safety Validation of a BREST-OD-300 Installation
4. OKBM Afrikantov Experience in Developing Methods and Computer Codes for Reliability Analysis and Probabilistic Safety Analysis of Nuclear Installations
5. Numerical Modeling of RBMK-1000 Graphite Stack Distortion
6. Cabaret-Sc1 Code Validation in Experiments on Hydrogen Explosion Safety at NPP
7. Recovery of the Surface Density of Radionuclide Contamination of Soil from Aerogamma Survey Data
8. Evaluation of Sokrat Code Possibility to Model Uranium-Dioxide Fuel Dissolution by Molten Zirconium
9. Computational Errors in the Calculation of Long Radioactive Decay Chains
10. Spot ZO S1, S2 Experiments: Numerical Analysis by Computational Hydrodynamics
11. Development and Verification of a Model of RVK-500, -1000 Recombiners for Modeling the Containment Shells of NPP with VVER by Computational Hydrodynamics
12. Two-Dimensional Thermohydraulic Module of the Integrated Code Sokrat-BN: Mathematical Model and Computational Results
13. Effect of the Operation of a Polar Crane on the Stress-Strain State of NPP Containment
14. Health Risk of Radon: Assessment Methods and Practical Applications
15. Probabilistic Strength Analysis of the Main Joint of a VVER-1000 Reactor
16. Reconstruction of the North-West Radioactive Track During the Accident at the Fukushima-1 Npp (Japan) Using Sokrat/V3 and Prolog Software
17. Reconstruction of the Eastern Urals Radioactive Track using the Prolog Software
18. Radiation Safety Validation of a BREST-OD-300 Installation
19. Socrat Code: Evaluation for Modeling the Destruction of RBMK Fuel Channels during Serious Accidents
20. Doping Uniformity Improvement of Emitter Cladding in NPP Electricity Generating Channels
21. Verification of an improved module for calculating fission products production in the industry code SOKRAT
22. A calculated basis for the strength and failureprobability of VVÉR contaiment
23. Modeling nuclide spreading during the accident in Bukhta Chazhma taking account of polydispersity and local orography
24. Actionable analysis of the accident at the fukushima-1 nuclear power plant (japan) and prediction of its consequences
25. Diffusion of fission-product dipole molecules in water vapor
26. Magnetism and anomalous properties of plutonium
27. Verification of the BONUS module integrated into the SOCRAT code
28. Expected radiological and radioecological consequences of operating floating nuclear heat and power plants
29. Development of a radiation-monitoring and emergency-response system in the Murmansk region
30. Analysis of the content of global 90Sr in the water and bottom deposits of reservoirs
31. Radiotoxicity at Final Transmutation of Actinides Accumulated in Transmutation Reactors
32. The Cost of Transmutation of Fission Products in Nuclear Reactors
33. Start of the Experiment on the Absolute Calibration of Particle Energy in VÉPP-4M near the τ-Lepton Production Threshold
34. Long-Lived-Radionuclide Transmutation Scenarios
35. More Effective Numerical Methods for Analyzing Thermomechanical Processes in the Components of Equipment in a Nuclear Power Plant
36. Special Features of the Calculation of the Stress–Strain State of VVÉR Second-Loop Pipelines with Erosion–Corrosion Thinning
37. Model of the Destruction of the Reactor in the No. 4 Unit of the Chernobyl Nuclear Power Plant
38. Investigation of the Solidification of Spent Filter Materials on Slags from the Leningrad Nuclear Power Plant
39. Possibilities for Improving Electronuclear Systems
40. Radiotoxicity and Residual Energy Release of Spent Uranium–Plutonium and Thorium Fuel during Prolonged Storage
41. Radiotoxicity and Residual Energy Release of Actinides and Fission Products of Spent VVÉR Fuel in Long-Term Storage
42. Conditions of Transmutation of Plutonium, Americium, and Curium in Nuclear Facilities
43. Deformation of the body of a vvér main circulation pump examined by holographic interferometry and finite-element methods
44. Scope for denaturizing weapons-grade plutonium in a subcritical heavy-water blanket of candu type
45. Post-accident survey of the unit 4 reactor of the Chernobyl nuclear power plant
46. Methods and results of an analysis of the nonlinear thermomechanics of crack development in a reactor vessel during accidents
47. How much nuclear fuel is present in the lavalike fuel-containing mass in the fourth power-generating unit of the chernobyl nuclear power plant?
48. Influence of thermomechanical prestressing on increasing the breaking strength of reactor vessel materials
49. Electronuclear power plants in future nuclear power production
50. Heat release during upward motion of a steam-water mixture along a cooled surface
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