Digital models for retrospective analysis of the structure of currents in the Neva Bay

The Neva Bay is a body of water located between the delta of the Neva River and Kotlin Island. The goal of the study was to develop a method for numerical modeling of the shallow water equation in the Neva Bay, based on the finite element method. To achieve this goal, we solved a number of tasks. First, we selected characteristic periods in the history of the Neva Bay and formed numerical modeling options while determining boundary conditions. Secondly, we determined the geometric characteristics of the computational domain for modeling options and formed a finite element mesh for each of the options. Then, we found a numerical solution of hydrodynamic problems in terms of determining values of current velocity vectors. Finally, we conducted a comparative analysis of the results of solving the hydrodynamic problem of the structure of currents in the Neva Bay in different periods of history. The changes in the velocity field occurred because of the construction of the fairway and the dams for the Complex of flood protection structures (CFPS) in St. Petersburg. Today there is practically no water flow south of the Sea Canal. Water exchange between the Neva Bay and the Gulf of Finland is carried out due to culvert structures in the northern part of the CFPS and navigation facilities. The average flow of the Neva River during the calculation period did not change and was about 2500 m3/s (depends on the water level in Lake Ladoga); an increase in speeds occurs north of the Sea Canal

Validation &Verification context for NPP design and construction

Nuclear power, as one of the most sophisticated and technologically advanced industry sectors, sets very demanding safety requirements. Fulfilment thereof is mostly to be implemented and justified at the design and construction stages. The process of Validation and Verification (V&V) for such facilities should cover all possible disciplines and cases, therefore a systematic approach to its organization is needed, which is not fully. The article objective is to determine the reasons for such strict safety requirements and explore the methods for achieving it, including the V&V process, as well as determining the factors (V&V dimensions) forming the V&V context, which is going to be used for choosing a specific type of V&V activities (to be conducted during the design and construction phases). Then, the article shall determine the interrelations between disciplines that use the V&V results depending on the context. V&V Context is setting up the parameters defining specific V&V activities. Generally, the V&V Context includes the following dimensions: Discipline (Construction, Electrical, Instrumentation and Control), Hierarchy (Design Levels – Plant, System, Components and Structures levels), NPP Construction Project phases (Design, Construction, Installation, Commissioning). The V&V process is a complex one and it will be different for each combination of the above-mentioned V&V dimensions together forming the V&V Context

Nuclear qualification process for systems, structures and components

The modern NPPs (Nuclear Power Plants) are the part of the very complex and demanding sector of industry. Its complexity is based on the innovate and the high-tech technologies, engineered safety features where the specific safety functions are to be performed to ensure the nuclear safety (as part of technosphere safety) and prevent radioactivity release, which consequently lead to the possible human losses and environmental disasters. Consequently, modern technologies incorporated in the design and construction of NPP (its systems, structure and components) shall be qualified to ensure its capability to perform designated safety functions in the demanded conditions, including harsh accident environment (qualified as intended) via the specific V&V activities. Thus, Qualification should not cover only the equipment, but the all: systems, structures and components (SSC), therefore a systematic approach to its organization and planning is needed, which is not fully presented in publications nowadays. The article objective is to define the SSC Qualification and its scope of application, identify the Functional and Environmental qualification and forming of the Qualification context. Then, the article determines the V&V actions that provide Qualification evidences

Validation &Verification context for NPP design and construction

Nuclear power, as one of the most sophisticated and technologically advanced industry sectors, sets very demanding safety requirements. Fulfilment thereof is mostly to be implemented and justified at the design and construction stages. The process of Validation and Verification (V&V) for such facilities should cover all possible disciplines and cases, therefore a systematic approach to its organization is needed, which is not fully. The article objective is to determine the reasons for such strict safety requirements and explore the methods for achieving it, including the V&V process, as well as determining the factors (V&V dimensions) forming the V&V context, which is going to be used for choosing a specific type of V&V activities (to be conducted during the design and construction phases). Then, the article shall determine the interrelations between disciplines that use the V&V results depending on the context. V&V Context is setting up the parameters defining specific V&V activities. Generally, the V&V Context includes the following dimensions: Discipline (Construction, Electrical, Instrumentation and Control), Hierarchy (Design Levels – Plant, System, Components and Structures levels), NPP Construction Project phases (Design, Construction, Installation, Commissioning). The V&V process is a complex one and it will be different for each combination of the above-mentioned V&V dimensions together forming the V&V Context

Nuclear qualification process for systems, structures and components

The modern NPPs (Nuclear Power Plants) are the part of the very complex and demanding sector of industry. Its complexity is based on the innovate and the high-tech technologies, engineered safety features where the specific safety functions are to be performed to ensure the nuclear safety (as part of technosphere safety) and prevent radioactivity release, which consequently lead to the possible human losses and environmental disasters. Consequently, modern technologies incorporated in the design and construction of NPP (its systems, structure and components) shall be qualified to ensure its capability to perform designated safety functions in the demanded conditions, including harsh accident environment (qualified as intended) via the specific V&V activities. Thus, Qualification should not cover only the equipment, but the all: systems, structures and components (SSC), therefore a systematic approach to its organization and planning is needed, which is not fully presented in publications nowadays. The article objective is to define the SSC Qualification and its scope of application, identify the Functional and Environmental qualification and forming of the Qualification context. Then, the article determines the V&V actions that provide Qualification evidences