Sökning: "System Thermal-Hydraulics"

Visar resultat 1 - 5 av 7 uppsatser innehållade orden System Thermal-Hydraulics.

  1. 1. Thermal-hydraulic safety analysis of the HTTU and GEMINI+ cores in TRACE

    Master-uppsats, KTH/Fysik

    Författare :Eva Joosten; [2022]
    Nyckelord :HTGR; TRACE; Thermal-Hydraulics; Safety; Heat Transfer; HTGR; TRACE; Termisk-Hydraulik; Säkerhet; Värmeöverföring;

    Sammanfattning : With the coming of Generation IV systems, there is a need for thermal-hydraulic codes to model such advanced reactors. Codes for High Temperature Gas-cooled Reactors (HTGRs) already exist, but often suffer from insufficient validation and little user experience. LÄS MER

  3. 2. Simulation of IB-LOCA in TRACE : A semi-blind study of numerical simulations compared to the PKL test facility

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

    Författare :Matilda Tiberg; [2022]
    Nyckelord :Pressurized Water Reactor; Safetey analysis; LOCA; Intermediate Break; PKL; TRACE; transient; thermal hydraulics;

    Sammanfattning : This thesis studied the performance of the thermal hydraulic software TRACE applied on an intermediate sized break (IB) happening on the cold leg in a pressurized water reactor (PWR), causing a loss-of-coolant accident (LOCA). The same accident has previously been simulated in the PKL Test Facility, which is a scaled version of a PWR and is used to simulate transients stemming from different accidents. LÄS MER

  4. 3. Thermal Hydraulics Simulations for Nuclear Energy

    Master-uppsats, Uppsala universitet/Tillämpad kärnfysik

    Författare :Wilhelm Thunberg; [2022]
    Nyckelord :Simulation; Thermal Hydraulics; Nuclear Energy; CFD; Sub-channel; System Codes; Trace; Cobra; DNS; LES; RANS;

    Sammanfattning : .... LÄS MER

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

    Master-uppsats, KTH/Kärnkraftssäkerhet

    Författare :XIAO HU; [2012]
    Nyckelord :LOCA; TRACE; thermal-hydraulics transient; sensitivity analysis;

    Sammanfattning : 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. LÄS MER

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

    Master-uppsats, KTH/Kärnkraftssäkerhet

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

    Sammanfattning : 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. LÄS MER