Essays about: "Kärnkraftssäkerhet"

Showing result 1 - 5 of 14 essays containing the word Kärnkraftssäkerhet.

  1. 1. Two-phase CFD Modelling and Validation : SH204X Master Thesis Project Report

    University essay from KTH/Kärnenergiteknik

    Author : Richard Härlin; [2022]
    Keywords : Master Thesis; Simulation; Validation; DEBORA; CFD; OpenFOAM; Boiling; Two-phase Thermal-Hydraulics; Fluid Mechanics; Nuclear Power Safety; Examensarbete; Simulering; Validering; DEBORA; CFD; OpenFOAM; Kokning; Tvåfas Termohydraulik; Kärnkraftssäkerhet;

    Abstract : This project deals with two-phase CFD model validation, a subject which is currently under active research due to its complexity. The goal is to create a model that predicts data profiles to an acceptable degree for a wide array of flow conditions. The applications within the nuclear field would mainly be for safety analysis, e.g. READ MORE

  3. 2. Applications of steel-plate composite structures for nuclear modular construction

    University essay from KTH/Betongbyggnad

    Author : Yann Vicedo; [2021]
    Keywords : nuclear concrete structures; modular construction; steel-plate composite modules; kärnkraftsbetongkonstruktioner; modulär konstruktion; kompositmoduler av stålplåt;

    Abstract : Despite being the world’s second most important low-carbon source of electricity, the development of nuclear capacities is limited and does not comply with the International Energy Agency’s Sustainable Development Scenario. One of the main reasons for this lack of development is high and increasing costs of new nuclear capacities. READ MORE

  4. 3. Influence of In-vessel Pressure and Corium Melt Properties on Global Vessel Wall Failure of Nordic-type BWRs

    University essay from KTH/Kärnkraftssäkerhet

    Author : Andrei Goronovski; [2013]
    Keywords : Severe accident; Vessel failure; CRGT cooling; Thermo-Mechanical creep analysis;

    Abstract : The goal of the present study is to investigate the effect of different scenarios of core degradation in a Nordic-type BWR (boiling water reactor) on the reactor pressure vessel failure mode and timing. Specifically we consider the effects of (i) in-vessel pressure, (ii) melt properties. READ MORE

  5. 4. TRACE Analysis of LOCA Transients Performed on FIX-II Facility

    University essay from KTH/Kärnkraftssäkerhet

    Author : XIAO HU; [2012]
    Keywords : LOCA; TRACE; thermal-hydraulics transient; sensitivity analysis;

    Abstract : As a latest developed computational code, TRACE is expected to be useful and effective for analyzing the thermal-hydraulic behaviors in design, licensing and safety analysis of nuclear power plant. However, its validity and correctness have to be verified and qualified before its application into industry. READ MORE

  6. 5. Validation of TRACE Code against ROSA/LSTF Test for SBLOCA of Pressure Vessel Upper-Head Small Break

    University essay from KTH/Kärnkraftssäkerhet

    Author : Mian Xing; [2012]
    Keywords : SBLOCA; LSTF; TRACE; thermal-hydraulics transient; safety analysis;

    Abstract : OECD/NEA ROSA/LSTF project tests are performed on the Large Scale Test Facility (LSTF). LSTF is a full-height, full-pressure and 1/48 volumetrically-scaled two-loop system which aims to simulate Japanese Tsuruga-2 Westinghouse-type 4-loop PWR. READ MORE