Sökning: "Pavel Kudinov"
Visar resultat 1 - 5 av 7 avhandlingar innehållade orden Pavel Kudinov.
1. Particulate Debris Spreading and Coolability
Sammanfattning : In Nordic design of boiling water reactors, a deep water pool under the reactor vessel is employed for the core melt fragmentation and the long term cooling of decay heated corium debris in case of a severe accident. To assess the effectiveness of such accident management strategy the Risk-Oriented Accident Analysis Methodology has been proposed. LÄS MER
2. Steam condensation in a water pool and its effect on thermal stratification and mixing
Sammanfattning : The Pressure Suppression Pool (PSP) of a Boiling Water Reactor (BWR) is a large heat sink designed to limit the containment pressure by condensing steam released from the primary coolant system. The development of thermal stratification is a safety concern since it leads to higher containment pressures than in completely mixed conditions, and can affect the performance of systems such as the emergency core cooling and containment spray, which the use PSP as a source of water. LÄS MER
3. Development of Risk Oriented Accident Analysis Methodology for Assessment of Effectiveness of Severe Accident Management Strategy in Nordic BWR
Sammanfattning : Nordic Boiling Water Reactor (BWR) design employs ex-vessel debris coolability as a severe accident management strategy (SAM). In case of a severe accident, the debris ejected from the vessel are expected to fragment, quench and form a debris bed, which is coolable by a natural circulation of water. LÄS MER
4. Validation and Application of CFD to Safety-Related Phenomena in Lead-Cooled Fast Reactors
Sammanfattning : Carbon-free nuclear power production can help to relieve the increasing energy demand in the world. New generation reactors with improved safety, sustainability, reliability, economy and security are being developed. Lead-cooled fast reactor (LFR) is one of them. LÄS MER
5. Application of a system thermal-hydraulics code to development of validation process for coupled STH-CFD codes
Sammanfattning : Generation IV reactors are designed to provide sustainable energy generation, minimize waste production and excel in safety. Due to lack of operational experience, ever evolving design and stringent safety requirements, these novel reactors have to rely heavily on simulations. LÄS MER