Sökning: "Ex-vessel melt coolability"

Visar resultat 1 - 5 av 7 avhandlingar innehållade orden Ex-vessel melt coolability.

  1. 1. Investigation of mechanisms for melt coolability with bottom coolant injection

    Författare :Domenico Paladino; KTH; []
    Nyckelord :Nuclear serve accident; Direct contact boiling; European Pressurized Reactor; Ex-vessel melt coolability; Melt coolability by bottom injection;

    Sammanfattning : .... LÄS MER

  3. 2. 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

  4. 3. MELCOR Capability Development for Simulation of Debris Bed Coolability

    Författare :Yangli Chen; Weimin Ma; Michael Buck; KTH; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Severe accident; coolability; MELCOR; COCOMO; surrogate modeling; coupling codes; uncertainty analysis.; Kärnenergiteknik; Nuclear Engineering;

    Sammanfattning : The severe accident management (SAM) strategy for a Nordic boiling water reactor (BWR) employs cavity flooding prior to vessel failure, so that the core melt (corium) discharged from the vessel could fragment and form a particulate debris bed. The key to the success of this SAM strategy is the coolability of ex-vessel debris beds. LÄS MER

  5. 4. Investigations of passive safety systems in LWRs : melt coolability with bottom coolant injection, light gas effects on a passive containment cooling system

    Författare :Domenico Paladdino; KTH; []
    Nyckelord :;

    Sammanfattning : The key objectives in introducing passive features in thesafety systems for Light Water Reactor (LWR) are to increasetheir reliability, to simplify the design of the plants and toimprove performance and economics. Component and integralsystem tests in scaled facilities are required for optimizingthe design and for certification of these safety systems. LÄS MER

  7. 5. Phenomenological and mechanistic modeling of melt-structure-water interactions in a light water reactor (LWR) severe accident

    Författare :Anh Bui Viet; KTH; []
    Nyckelord :;

    Sammanfattning : Severe accidents in light water reactors have been the fotalpoint of much research, performed in the last two decades,aimed at understarrding the inherent physical phenomena and toevaluate proposed accident management schemes for mitigatingthe consequences of such accidents. Severe accident progressionand consequences, av the reactor core overheats and melts, areintimately related to the interactions of the melt with coolant(water) and structures. LÄS MER