Sökning: "Kärnkraftssäkerhet"
Visar resultat 1 - 5 av 18 uppsatser innehållade ordet Kärnkraftssäkerhet.
1. Utvecklingsbehov av probabilistisk säkerhetsanalys (PSA) för applicering på SMR:er
Uppsats för yrkesexamina på avancerad nivå, Uppsala universitet/Tillämpad kärnfysikSammanfattning : Nuclear power is an important part of Sweden's energy system and contributes with about 30 % of the supplied electric energy. Interest in new construction is currently high and one type of reactor that may be built is small modular reactors, SMRs. LÄS MER
2. Förbättring av kärnkraftssäkerhet genom erfarenhetsåterföring : En benchmarkingstudie för att identifiera bästa praxis
Uppsats för yrkesexamina på avancerad nivå, Uppsala universitet/Avdelningen Vi3Sammanfattning : The existence and viability of nuclear power have been at the center of debate for several decades due to the inherent safety risks. Disasters such as Three Mile Island (1979), Chernobyl (1986), and Fukushima Daichii (2011) have resulted in severe consequences but have also led to higher safety standards and precautionary measures within the nuclear industry. LÄS MER
3. Two-phase CFD Modelling and Validation : SH204X Master Thesis Project Report
Master-uppsats, KTH/KärnenergiteknikSammanfattning : This project deals with two-phase CFD model validation, a subject which is currently under active research due to its complexity. The goal is to create a model that predicts data profiles to an acceptable degree for a wide array of flow conditions. The applications within the nuclear field would mainly be for safety analysis, e.g. LÄS MER
4. Applications of steel-plate composite structures for nuclear modular construction
Master-uppsats, KTH/BetongbyggnadSammanfattning : Despite being the world’s second most important low-carbon source of electricity, the development of nuclear capacities is limited and does not comply with the International Energy Agency’s Sustainable Development Scenario. One of the main reasons for this lack of development is high and increasing costs of new nuclear capacities. LÄS MER
5. Influence of In-vessel Pressure and Corium Melt Properties on Global Vessel Wall Failure of Nordic-type BWRs
Master-uppsats, KTH/KärnkraftssäkerhetSammanfattning : The goal of the present study is to investigate the effect of different scenarios of core degradation in a Nordic-type BWR (boiling water reactor) on the reactor pressure vessel failure mode and timing. Specifically we consider the effects of (i) in-vessel pressure, (ii) melt properties. LÄS MER