Sökning: "thermal-hydraulics"

Visar resultat 1 - 5 av 13 avhandlingar innehållade ordet thermal-hydraulics.

  1. 1. 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

  2. 2. 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

  3. 3. 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

  4. 4. Development of fine-mesh methodologies for coupled calculations in Light Water Reactors

    Författare :Klas Jareteg; Chalmers University of Technology; []
    Nyckelord :NATURVETENSKAP; TEKNIK OCH TEKNOLOGIER; NATURAL SCIENCES; ENGINEERING AND TECHNOLOGY; CFD; Coupled neutronics thermal-hydraulics; nuclear reactor multiphysics; multiphase flow;

    Sammanfattning : This thesis presents fine-mesh multiphysics methodologies and algorithms for numerical predictions of the behavior of Light Water Reactor (LWR) cores. The multiphysics aspects cover the distribution of neutrons, the fluid flow of the coolant and the conjugate heat transfer between the solid fuel pins and the fluid coolant. LÄS MER

  5. 5. Sensitivity and Uncertainty Analysis of Boiling Water Reactor Stability Simulations

    Författare :Ivan Gajev; Weimin Ma; Tomasz Kozlowski; Kostadin Ivanov; KTH; []

    Sammanfattning : The best estimate codes are used for licensing of Nuclear Power Plants (NPP), but with conservative assumptions. It is claimed that the uncertainties are covered by the conservatism of the calculation. LÄS MER