Search for dissertations about: "corium flow"

Showing result 1 - 5 of 8 swedish dissertations containing the words corium flow.

  1. 1. Computation of convective two- and three-dimensional flow patterns with phase change

    Author : George Fileas; [1991]
    Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; nuclear reactor safety; corium flow; finite-difference principle; 3-D computations; solidification; long-term heat storage;

    Abstract : .... READ MORE

  2. 2. Analysis methodology for RBMK-1500 core safety and investigations on corium coolabiblty during a LWR sever accidnet

    University dissertation from Stockholm : Energiteknik

    Author : Audrius Jasiulevicius; [2004]
    Keywords : RBMK. Light water reactor. Core analysis; transient analysis; reactor dynamics;

    Abstract : This thesis presents the work involving two broad aspectswithin the field of nuclear reactor analysis and safety. Theseare: - development of a fully independent reactor dynamics andsafety analysis methodology of the RBMK-1500 core transientaccidents and - experiments on the enhancement of coolabilityof a particulate bed or a melt pool due to heat removal throughthe control rod guide tubes. READ MORE

  3. 3. Input Calibration, Code Validation and Surrogate Model Development for Analysis of Two-phase Circulation Instability and Core Relocation Phenomena

    University dissertation from Stockholm : Kungliga Tekniska högskolan

    Author : Viet-Anh Phung; Pavel Kudinov; Cristophe Demaziere; [2017]
    Keywords : NATURVETENSKAP; NATURAL SCIENCES; Reactor system code; input calibration; code validation; surrogate model; two-phase circulation flow instability; in-vessel core relocation; genetic algorithm; artificial neural network; Reaktorsystemkod; indata kalibrering; kodvalidering; surrogatmodell; två-fas cirkulationsflöde; instabilitet; härdrelokering i reaktortanken; genetisk algoritm; artificiella neurala nätverk; Physics; Fysik;

    Abstract : Code validation and uncertainty quantification are important tasks in nuclear reactor safety analysis. Code users have to deal with large number of uncertain parameters, complex multi-physics, multi-dimensional and multi-scale phenomena. READ MORE

  4. 4. Particulate Debris Spreading and Coolability

    University dissertation from Stockholm : Kungliga Tekniska högskolan

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

    Abstract : 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. READ MORE

  5. 5. Numerical Investigations on Debris Bed Coolability and Mitigation Measures in Nordic Boiling Water Reactors

    University dissertation from KTH Royal Institute of Technology

    Author : Zheng Huang; Weimin Ma; Florian Fichot; [2019]
    Keywords : TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; Severe accident; Debris bed; Coolability; Quench; Oxidation; MEWA code; Coupled analysis; Svåra haverier; Grusbädd; Kylbarhet; Kylning; Oxidering; MEWA program; Kopplad analys; Physics; Fysik;

    Abstract : This thesis is aiming at coolability assessment of particulate debris beds formed in hypothetical severe accidents of Nordic boiling water reactors (BWRs) which may employ either lower drywell flooding or control rod guide tubes (CRGT) cooling as severe accident management strategies. For this purpose, quench and cooling limit (dryout) of debris beds after their formation from fuel coolant interactions were investigated by numerical simulations using the MEWA code. READ MORE