Sökning: "RELAP5"

Visar resultat 1 - 5 av 7 avhandlingar innehållade ordet RELAP5.

  1. 1. Development of Effective Algorithm for Coupled Thermal-Hydraulics – Neutron-Kinetics Analysis of Reactivity Transient

    Författare :Joanna Peltonen; Tomas Lefvert; Paolo Vinai; KTH; []
    Nyckelord :Light Water Reactor; BWR; RELAP5; PARCS; Coupling TH NK; Mapping; Spatial Refinement; Turbine Trip; Feedwater Transient; Control Rod Drop; Reactor Stability;

    Sammanfattning : Analyses of nuclear reactor safety have increasingly required coupling of full three dimensional neutron kinetics (NK) core models with system transient thermal-hydraulics (TH) codes. To produce results within a reasonable computing time, the coupled codes use different spatial description of the reactor core. LÄS MER

  2. 2. Effective Spatial Mapping for Coupled Code Analysis of Thermal–Hydraulics/Neutron–Kinetics of Boiling Water Reactors

    Författare :Joanna Peltonen; Weimin Ma; Maria Avramova; KTH; []
    Nyckelord :NATURAL SCIENCES; NATURVETENSKAP; NATURVETENSKAP; NATURAL SCIENCES; Boiling Water Reactor; RELAP5; TRACE; PARCS; Coupled TH NK analysis; Spatial Mapping; Turbine Trip; Feedwater Transient; Control Rod Drop; Reactor Stability; Hierarchical Clustering; kokvattenreaktor; reaktoranalys; RELAP5; TRACE; PARCS; TH NK analys; turbin tripp; matarvatten transient; fallande styrstav; reaktor stabilitet; hierarkisk klustringsmetodik; SRA - Energy; SRA - Energi;

    Sammanfattning : Analyses of nuclear reactor safety have increasingly required coupling of full three dimensional neutron kinetics (NK) core models with system transient thermal–hydraulics (TH) codes.  In order to produce results within a reasonable computing time, the coupled codes use two different spatial description of the reactor core. LÄS MER

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

    Författare :Viet-Anh Phung; Pavel Kudinov; Cristophe Demaziere; KTH; []
    Nyckelord :NATURAL SCIENCES; NATURVETENSKAP; 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;

    Sammanfattning : 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. LÄS MER

  4. 4. Application of a system thermal-hydraulics code to development of validation process for coupled STH-CFD codes

    Författare :Kaspar Kööp; Pavel Kudinov; Mariano Tarantino; KTH; []
    Nyckelord :Physics; Fysik;

    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

  5. 5. Development and Applications of a General Coupled Thermal-hydraulic/Neutronic Model for the

    Författare :Mathias Stålek; Chalmers University of Technology; []
    Nyckelord :TEKNIK OCH TEKNOLOGIER; TEKNIK OCH TEKNOLOGIER; ENGINEERING AND TECHNOLOGY; ENGINEERING AND TECHNOLOGY; reactor transients; measurements; thermal-hydraulics; core calculations; coupled calculations;

    Sammanfattning : Coupled calculations are important for the simulation of nuclear power plants when there is a strongfeedback between the neutron kineticsand the thermal-hydraulics. A general coupled model of the Ringhals-3 Pressurized Water Reactor has beendeveloped for this purpose. LÄS MER