Sökning: "kokvattenreaktorer"

Visar resultat 1 - 5 av 7 avhandlingar innehållade ordet kokvattenreaktorer.

  1. 1. Climatic conditions inside nuclear reactor containments : Evaluation of moisture condition in the concrete within reactor containments and interaction with the ambient compartments

    Författare :Mikael OXFALL; Avdelningen för Byggnadsmaterial; []
    Nyckelord :kärnkraft; betong; in situ mätningar; relativ fuktighet; kokvattenreaktorer; tryckvattenreaktorer; masstransport;

    Sammanfattning : Safety is the top priority at a nuclear facility. The nuclear power plants are designed to prevent radioactive leakage to the surroundings, both during normal operation as well as in case of a severe accident. One of the most important structures in a nuclear power plant, with regard to safety, is thus the reactor containment wall. LÄS MER

  3. 2. Thermo-mechanical Assessment of Reactor Pressure Vessels of Light Water Reactors During Severe Accidents

    Författare :Hongdi Wang; Walter Villanueva; Sevostian Bechta; Weimin Ma; Artem Kulachenko; Michael Fitzpatrick; KTH; []
    Nyckelord :Severe accident scenario; reactor pressure vessel; in-vessel melt retention; failure analysis; finite element analysis; validations; Scenario för svåra haverier; reaktortank; in-vessel retention; feleffektsanalys; Finite Element Analyser; validering; Physics; Fysik;

    Sammanfattning : The reactor pressure vessel (RPV) is one of the crucial safety barriers designed to isolate the reactor core, safeguarding against potential radioactive releases into the environment during a severe accident. The assessment of RPV behaviour and its failure is necessary to predict the characteristics of melt release into the reactor pit and succeeding ex-vessel accident progression. LÄS MER

  4. 3. Particulate Debris Spreading and Coolability

    Författare :Simone Basso; Pavel Kudinov; Florian Fichot; KTH; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Self-leveling; debris bed; spreading; coolability; severe accident; probabilistic framework; Monte Carlo; uncertainty; sensitivity; Fysik; Physics;

    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

  5. 4. Modelling of intergranular stress corrosion cracking mechanism : Du som saknar dator/datorvana kan kontakta [email protected] för information

    Författare :Michal Sedlak Mosesson; Bo Alfredsson; Thierry Couvant; KTH; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Cohesive Zone Model; Fracture Mechanics; Diffusion; Duplex oxide; Multi-physics; Finite Element Model; Engineering Mechanics; Teknisk mekanik;

    Sammanfattning : When assessing nuclear power plant life, stress corrosion cracking (SCC) plays an important role. Stress corrosion cracking in nuclear power plants is well recognized and heavily researched. Still due to its complicated nature it is not completely understood. There are many different damage mechanisms behind SCC. LÄS MER

  7. 5. Experimental and analytical study of thermal mixing at reactor conditions

    Författare :Mattia Bergagio; Henryk Anglart; Horst-Michael Prasser; KTH; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; High-cycle thermal fatigue; Hilbert-Huang transform; large eddy; WALE; rainflow; inverse heat conduction; adjoint conjugate gradient; Energy Technology; Energiteknik; Fysik; Physics;

    Sammanfattning : High-cycle thermal fatigue due to turbulent mixing of streams at distinct temperatures is an interdisciplinary issue affecting safety and life extension of existing reactors together with the design of new reactors. It is challenging to model damage and thermal loads arising from the above mixing. LÄS MER