A5005918167- Nuclear Materials and Properties
- Nuclear reactor physics and engineering
- Nuclear Engineering Thermal-Hydraulics
- Nuclear and radioactivity studies
- Combustion and Detonation Processes
- Graphite, nuclear technology, radiation studies
- Radioactive contamination and transfer
- Radioactive element chemistry and processing
- Fluid Dynamics and Mixing
- Advanced Data Processing Techniques
- Thermodynamic and Structural Properties of Metals and Alloys
- Metallurgical Processes and Thermodynamics
- Disaster Response and Management
- Cyclone Separators and Fluid Dynamics
- Boron and Carbon Nanomaterials Research
- Heat Transfer and Boiling Studies
- Wind and Air Flow Studies
- Iron and Steelmaking Processes
- Radioactivity and Radon Measurements
- Meteorological Phenomena and Simulations
- Particle Dynamics in Fluid Flows
- Risk and Safety Analysis
Nuclear Safety Institute
2013-2024
Russian Academy of Sciences
2013-2024
This paper considers the issues of safety assessment new nuclear power plant (NPP) projects with VVER Generation III+ reactors in relation to probability target for large release, which is subject verification development a full-scale Probabilistic Safety Assessment (PSA) Level 2. The design solutions implemented allow reducing severe accident (SA) due internal initial events level 10−7/year. Exceeding radioactive release criterion may thus be related mainly consequences beyond-design...
We report an ensemble approach applied to the radiation dose modeling for a hypothetical emergency with long-term release of radioactive materials into atmosphere. The study is aimed at improving response system in Russia and focuses on quantifying impact meteorological uncertainties atmospheric dispersion transport. Four sets options conditions are used: (i) classic global weather forecast (zero member), (ii) 21 members, (iii) analysis, (iv) real local measurements. numerical experiments...
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Dependence of the CPU time needs for calculation source term during a severe accident at nuclear power plants with WWER reactors from individual physical processes and phenomena used as part tools similar to SOСRAT/V3 code is investigated. This analysis allows revealing most expensive models in terms runtime. The simplification these can ensure greatest acceleration calculation. relevance task draws need develop new or adapt existing assessing intensity radioactive emission sources tasks...
The article describes a model for calculating the containment thermal in severe accidents at nuclear power plants with water coolant. is implemented SOCRAT integral code form of CONT_TH module, which allows performing self-consistent calculation parameters VVER reactor plant and during accident. In conjunction other modules code, realistic transfer radioactive substances to provided, necessary calculate source term into environment when justifying safety plants, including probability...
The paper presents the results of qualification analysis experimental data on high-temperature oxidation Russian zirconium alloys in steam, which include an assessment consistency measurement tests, and numerical modeling experiments with SOCRAT-V1/V2 code. Conclusions are provided possibility using SSC RIAR programs for validation severe accident codes, applicability code prediction claddings fuel rods.
Specialized computer codes that model the behavior of aerosol particles propagating through a system pipes or air ducts are used for assessment particle deposition. Developed in Russia, SOCRAT/V3 is one such code. was modeling transport radioactive aerosols containing 137Cs radionuclide an duct during real emergency. The obtained results were to estimate exposure dose rate (EDR) gamma radiation near duct. estimation compared with data measurements gamma-radiation EDR along duct.This paper...
The paper presents the results of numerical modeling for ballooning and burst fuel rods claddings made domestic foreign alloys. integral code SOCRAT-V1/V2 is used as a means modeling. uncertainty analysis calculation to input uncertainties temperature pressure measurements was performed. demonstrate good qualitative quantitative compliance with measured times cladding failure under partial core uncovery conditions. validation evidence on importance performing new experiments rod burst.