Sökning: "nuclear reactor pressure vessel"

Visar resultat 1 - 5 av 8 uppsatser innehållade orden nuclear reactor pressure vessel.

  1. 1. Modellering, simulering och analys av kärnreaktorn BWRX-300

    Uppsats för yrkesexamina på avancerad nivå, Uppsala universitet/Tillämpad kärnfysik

    Författare :Erik Backlund; [2023]
    Nyckelord :Kärnkraft; SMR; små modulära reaktorer; liten modulär reaktor; kärnreaktor; BWR; BWRX-300; självcirkulation; passiv säkerhet; GE Hitachi; cykellängd; härddesign; nukleär design; Simulate5; GNF2; kärnbränsle; reaktormodell;

    Sammanfattning : The demand for fossil-free energy production is rising due to electrification and increased consumption in the energy system. There are also multiple climate goals to reach, to preserve the possibilities of a sustainable future. LÄS MER

  3. 2. Implementation of 3D-Imaging technique for visual testing in a nuclear reactor pressure vessel

    Master-uppsats, KTH/Maskinkonstruktion (Inst.)

    Författare :André Tanco; [2014]
    Nyckelord :Dekra Industrial AB; Visual testing; Imaging technique; Structural light; Dekra Industrial AB; Visuell inspektion; Avbildningsteknik; Strukturerat ljus;

    Sammanfattning : This master thesis has been performed by request of Dekra Industrial AB. Dekra Industrial AB is a Swedish subsidiary company of the German company Dekra and works for example with safety inspections within the nuclear power industry. LÄS MER

  4. 3. CFD simulation of pool dynamics in a nuclear reactor's condensation pool

    Uppsats för yrkesexamina på avancerad nivå, Uppsala universitet/Tillämpad kärnfysik

    Författare :Anders Jansson; [2014]
    Nyckelord :CFD; computational fluid dynamics; condensation pool; pool dynamics; nuclear reactor; CFD; beräkningsströmningsdynamik; kondensationsbassäng; pooldynamik; kärnkraftsreaktor;

    Sammanfattning : In a nuclear reactor the containment protects the environment from radioactive emissions. It is separated in two parts, a drywell and a wetwell. The drywell contains the reactor vessel and the steam pipes. If a steam leakage occurs in this part of the containment the pressure will increase. LÄS MER

  5. 4. CFD-analysis of buoyancy-driven flow inside a cooling pipe system attached to a reactor pressure vessel

    Master-uppsats, Linköpings universitet/Mekanisk värmeteori och strömningslära; Linköpings universitet/Tekniska högskolan

    Författare :Jens Petersson; [2014]
    Nyckelord :CFD; OpenFOAM; LES; nuclear reactor pressure vessel;

    Sammanfattning : In this work a cooling system connected to a reactor pressure vessel has been studied using the CFD method for the purpose of investigating the strengths and shortcomings of using CFD as a tool in similar fluid flow problems within nuclear power plants. The cooling system is used to transport water of 288K (15°C) into a nuclear reactor vessel filled with water of about 555K (282°C) during certain operating scenarios. LÄS MER

  7. 5. Investigation of Conditions for Activation of Rupture Disk in BWR Containment Filtering System

    Master-uppsats, KTH/Kärnkraftssäkerhet

    Författare :Guillem Beltran Arroyos; [2011]
    Nyckelord :GOTHIC software; rupture disk; large LOCA;

    Sammanfattning : Due to the Three Mile Island accident in 1979 the Swedish government took the decision in 1986 to impose a pressure relief system for Swedish BWR’s which prevents containment overpressure in case of LOCA. This pressure relief system consists of a rupture disks in two different systems, non-filtered system 361 and filtered system 362. LÄS MER